Event Notification Report for December 7, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/06/2000 - 12/07/2000
** EVENT NUMBERS **
37557 37572 37573
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37557 |
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| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 11/30/2000|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 12:03[EST]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 11/30/2000|
+------------------------------------------------+EVENT TIME: 08:44[EST]|
| NRC NOTIFIED BY: CHARLES MORRIS |LAST UPDATE DATE: 12/06/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |EDWARD MCALPINE R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| LOSS OF SAFETY FUNCTION OF THE NUCLEAR SERVICES SEA WATER SYSTEM |
| |
| At 0843 on November 30, 2000, RWP-2B. Nuclear Services Sea Water Pump, was |
| started and observed to develop low discharge pressure, rendering the pump |
| INOPERABLE. This condition was caused by diversion of flow via a failed |
| open check valve upon shutdown of pump, RWP-1 which shares a common |
| discharge header with pump RWP-2B. |
| |
| RWP-2A, Nuclear Services Sea Water Pump, discharge is also common to RWP-2B. |
| Consequently, RWP--2A would likely not have developed adequate discharge |
| pressure, and therefore, adequate flow could not have been provided by |
| either Nuclear Services Sea Water Pump. |
| |
| Although allowed by design, this single failure defeats the safety function |
| of the Nuclear Services Sea Water System. |
| |
| The licensee notified the NRC resident inspector. |
| |
| * * * RETRACTION ON 12/06/00 AT 1920 ET BY BILL BANDHAUER TAKEN BY MACKINNON |
| * * * |
| |
| On December 6, 2000, FPC performed further evaluation of the required safety |
| function and the pertinent plant conditions observed during this event. |
| Even with the partially stuck open check valve, sufficient capacity of |
| system pumps and heat exchangers remained to remove design basis heat loads. |
| FPC has concluded that the Nuclear Services Sea Water System would have |
| performed the required heat removal safety function, if called upon. |
| |
| Additionally, FPC considered the impact of increased electrical loading on |
| the Emergency Diesel Generators caused by increased pump flow rate. FPC |
| concluded that the electrical diesel generators remained capable of |
| supporting the required electrical loads. |
| |
| Based upon these additional evaluations, FPC determined that this condition |
| in not reportable and therefore, retracts this event. R2DO (Paul |
| Fredrickson) notified. |
| |
| |
| The NRC Resident Inspector will be notified of this retraction by the |
| licensee. |
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|General Information or Other |Event Number: 37572 |
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| REP ORG: ARIZONA RADIATION REGULATORY AGENCY |NOTIFICATION DATE: 12/06/2000|
|LICENSEE: DAMES AND MOORE |NOTIFICATION TIME: 11:38[EST]|
| CITY: TUCSON REGION: 4 |EVENT DATE: 12/06/2000|
| COUNTY: STATE: AZ |EVENT TIME: [MST]|
|LICENSE#: 07-228 AGREEMENT: Y |LAST UPDATE DATE: 12/06/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BLAIR SPITZBERG R4 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: AUBREY GODWIN (VIA FAX) | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT INVOLVING TWO STOLEN MOISTURE DENSITY GAUGES |
| |
| "This First Notice constitutes EARLY notice of events of POSSIBLE safety or |
| public interest significance. The information is as initially received |
| WITHOUT verification or evaluation, and is basically all that is known by |
| the Agency Staff at this time. |
| |
| "Date: December 6, 2000 |
| Time: 9:00 AM (MST) |
| First Notice: 00-16 |
| |
| "Arizona Licensee: Dames and Moore |
| License No. 07-228 |
| 7500 North Dreamy Draw Drive |
| Phoenix, AZ 857020 |
| |
| "At approximately 2:00 PM, December 5, 2000, the Agency received a report |
| advising that 2 Troxler Model 3440 moisture/density gauges were missing. |
| This information was supplied by the Dames and Moore Radiation Safety |
| Officer. The information supplied indicated that the LICENSEE was unsure |
| when the gauges were taken. They were last seen on December 4, 2000 in a |
| locked storage building at 1790 East River Road, Tucson, AZ. Each gauge |
| contains a 8 millicurie cesium 137 source and a 44 millicuries Americium 241 |
| :Beryllium source. The serial numbers for the gauges are 13024 and 17318. |
| The storage building was locked and had 24 hour security guard surveillance. |
| The lock had been cut. Tucson PD is investigating this matter. The LICENSEE |
| is offering a $500.00 reward. The Agency will be issuing a press release. |
| |
| "The LICENSEE and the Agency continue to investigate this event. |
| |
| "The states of Utah, California, Colorado, New Mexico, and Nevada together |
| with the U.S. NRC, the U.S. FBI and Mexico are being notified of this |
| event." |
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|Power Reactor |Event Number: 37573 |
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| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 12/06/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 11:48[EST]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 12/06/2000|
+------------------------------------------------+EVENT TIME: 09:42[CST]|
| NRC NOTIFIED BY: CURT STEFFES |LAST UPDATE DATE: 12/06/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL PARKER 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| REACTOR SCRAM - LOW REACTOR VESSEL WATER LEVEL |
| |
| An automatic reactor scram occurred on low reactor vessel water level. All |
| systems responded as expected. Operators noted lowering reactor vessel |
| water level and were attempting to respond to the problem when the low |
| reactor vessel water scram setpoint was reached. The lowest water level |
| seen during the transient was |
| -10", neither HPCI nor RCIC started. Reactor feedwater was maintained |
| throughout the event. Recirculation pumps are running and decay heat is |
| being removed by steaming to the main condenser. The cause of the feedwater |
| transient is under investigation. |
| |
| The licensee notified NRC resident inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021