Event Notification Report for December 28, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/27/2000 - 12/28/2000
** EVENT NUMBERS **
37559 37634 37635 37636
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37559 |
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| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 11/30/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 20:55[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/30/2000|
+------------------------------------------------+EVENT TIME: 17:00[EST]|
| NRC NOTIFIED BY: STEVE SAUER |LAST UPDATE DATE: 12/27/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANIELLO DELLA GRECA R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| SERVICE WATER ACCUMULATOR LEVEL HIGH OUT OF SPECIFICATION |
| |
| At 1700 on 11/30/00, it was identified that the 11B service water |
| accumulator level was higher than that allowed by technical specifications. |
| This was identified following a level device calibration. The service water |
| accumulators support containment integrity by ensuring the containment fan |
| coils remain properly filled during a design basis accident. Tech Spec |
| 3.6.1.1 and 3.6.2.3 were entered for containment integrity and the |
| inoperability of 11 and 12 containment fan coil units. Actions were taken |
| within the one hour time requirement to comply with the containment |
| integrity LCO. The service water accumulator was subsequently drained to |
| within specification at 1742. Tech Spec 3.6.11 was exited at this time. |
| The 11 and 12 containment fan coils were restored to operable at 1745 and |
| Tech Spec 3.6.2.3 was exited. Actions are underway to calibrate the |
| redundant instrumentation and to investigate the cause of the instrument |
| drift. All power plant parameters remained stable throughout this event and |
| no other safety systems were affected. |
| |
| The licensee notified the NRC resident inspector. |
| |
| * * * RETRACTION ON 12/27/00 AT 1053ET BY BASHORE TAKEN BY MACKINNON * * * |
| |
| A review of the actual service water accumulator parameters that existed |
| when the 11 service water accumulator level was high out of specification |
| was performed. Based on the actual service water accumulator pressure, |
| level and temperature and the service water inlet temperature that existed, |
| engineering has determined that the 11 service water accumulator would have |
| been able to perform its design basis function if called upon to do so |
| during the time that the accumulator level was high out of specification. |
| |
| Since the 11 service water accumulator was capable of performing its design |
| basis function, the above report is being retracted. NRC R1DO (L. |
| Doerflein) notified. |
| |
| |
| The NRC Resident Inspector was notified of this retraction by the licensee. |
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|Power Reactor |Event Number: 37634 |
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| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 12/27/2000|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 12:47[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 12/27/2000|
+------------------------------------------------+EVENT TIME: 10:31[EST]|
| NRC NOTIFIED BY: RANDY HAISLET |LAST UPDATE DATE: 12/27/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LAWRENCE DOERFLEIN R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|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 |
| | |
| | |
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EVENT TEXT
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| REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) DECLARED INOPERABLE |
| |
| The licensee was performing the procedure to reset the RCIC isolation, after |
| a surveillance was completed, when the closed inboard steam isolation valve |
| (MO-1301-16) went to dual indication while opening the outboard steam |
| isolation valve (MO-1301-17). Both steam isolation valves to the RCIC |
| turbine were closed and the RCIC system was declared inoperable. The |
| licensee is investigating the problem. |
| |
| Active limiting conditions for operation were entered for the RCIC system |
| and the primary containment isolation function of the RCIC inboard steam |
| isolation valve (MO-1301-16). |
| |
| The licensee notified the NRC Resident Inspector. |
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|General Information or Other |Event Number: 37635 |
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| REP ORG: NC DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 12/27/2000|
|LICENSEE: CHARLOTTE-MECKLENBURG HOSPITAL AUTHOR|NOTIFICATION TIME: 15:52[EST]|
| CITY: CHARLOTTE REGION: 2 |EVENT DATE: 12/27/2000|
| COUNTY: STATE: NC |EVENT TIME: 14:20[EST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 12/27/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MARK LESSER R2 |
| |SUSAN SHANKMAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: GEORGE ACCATTATO | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| DELIVERY VEHICLE WRECK WHILE CARRYING RADIOACTIVE MATERIAL, NO |
| CONTAMINATION |
| |
| On 12/22/00 a Courier Dispatch was involved in an accident while |
| transporting a Mo-99 generator, incident number ICD-00-47. The accident |
| occurred in Monroe, NC at the intersection of highways 116 and 74, about a |
| half mile from the delivery point, Union Regional Med Center Nuc Med. The |
| Radiation Safety Officer (RSO) went to the scene and made a determination of |
| no contamination on the driver, vehicle, or package outside. The package, |
| no apparent damage, was transferred to Union Regional Med Center Nuc Med. |
| There was no other radioactive material in the transport. |
| |
| The incident has been closed and a written report to the NRC will follow. |
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|Power Reactor |Event Number: 37636 |
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| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 12/27/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 18:03[EST]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 12/27/2000|
+------------------------------------------------+EVENT TIME: 13:30[CST]|
| NRC NOTIFIED BY: JEFFREY EASLEY |LAST UPDATE DATE: 12/27/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| HIGH PRESSURE CORE INJECTION (HPCI) SYSTEM DISCOVERED INOPERABLE |
| |
| "On 12/27/00 at 1330 hours QCOS 2300-09 (U-1 HPCI Vent Verification) was in |
| progress following QCOS 2300-11 (CCST/Torus Level Switch Functional |
| Testing). During the process of vent verification of the U-1 HPCI system, |
| the vent valves were open approximately 6.5 minutes prior to receiving water |
| through the vent lines; the U-1 HPCI system was found inoperable. |
| Performance acceptance criteria of QCOS 2300-09 states that venting times |
| >40 seconds could he construed as a preconditioning action per NRC IN 97-16 |
| and as such the U-1 HPCI system possibly could not have performed its' |
| safety function prior to the venting that took place on 12/27/00 at 1330. |
| The last successful vent of the U-1 HPCI system was completed on 11/30/00. |
| An investigation is underway to try to determine the time of the loss of |
| fill and the cause. This 4-hour ENS notification is being made in accordance |
| with 10 CFR 50.72(b)(2)(iii)(D)." |
| |
| The licensee notified the NRC Resident Inspector. |
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