Event Notification Report for November 7, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/06/2000 - 11/07/2000
** EVENT NUMBERS **
37492 37493 37494 37495 37496 37497 37498
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|Power Reactor |Event Number: 37492 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 11/06/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 05:29[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 11/06/2000|
+------------------------------------------------+EVENT TIME: 03:38[CST]|
| NRC NOTIFIED BY: DOUG HITZEL |LAST UPDATE DATE: 11/06/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PHIL HARRELL R4 |
|10 CFR SECTION: | |
|DDDD 73.71 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 90 Power Operation |90 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| 1-HOUR SECURITY REPORT |
| |
| SAFEGUARDS SYSTEM DEGRADATION RELATED TO PERIMETER MONITORING. IMMEDIATE |
| COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE WILL INFORM THE |
| NRC RESIDENT INSPECTOR. CONTACT THE HEADQUARTERS OPERATIONS OFFICER FOR |
| ADDITIONAL DETAILS. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37493 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ARIZONA RADIATION REGULATORY AGENCY |NOTIFICATION DATE: 11/06/2000|
|LICENSEE: PHELPS DODGE, BAGDAD, INC. |NOTIFICATION TIME: 12:29[EST]|
| CITY: BAGDAD REGION: 4 |EVENT DATE: 11/06/2000|
| COUNTY: YAVAPAI STATE: AZ |EVENT TIME: 10:00[MST]|
|LICENSE#: 13-005 AGREEMENT: Y |LAST UPDATE DATE: 11/06/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOE TAPIA R4 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+JOHN DAVIDSON, NMSS IAT |
| NRC NOTIFIED BY: AUBREY V. GODWIN |GAIL GOOD, REGON 4 IAT |
| HQ OPS OFFICER: LEIGH TROCINE |ROBERT MANILI, NRR IAT |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| ARIZONA RADIATION REGULATORY AGENCY REPORT REGARDING A SOURCE MISSING FROM |
| PHELPS DODGE, BAGDAD, INC. IN BAGDAD, ARIZONA |
| |
| The following text is a portion of a facsimile received from the Arizona |
| Radiation Regulatory Agency: |
| |
| "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: November 6, 2000 |
| Time: 10:00 AM (MST) |
| First Notice: 00-12 |
| Arizona Licensee: Phelps Dodge, Bagdad, Inc. [...] |
| License No. 13-005 [...]" |
| |
| "At approximately 11:30 AM, October 30, 2000, the Agency received a letter |
| advising that a Cadmium-109 source was missing. This information was |
| supplied by the Radiation Safety Officer. The information supplied |
| indicated that the LICENSEE was unsure when the source disappeared. Agency |
| inspection reports indicate that the last time that the LICENSEE reported |
| seeing the source [was on a January 1998 inventory]. The missing source is |
| a Texas Nuclear Model 696782, Serial Number LU-6484. The source [contained] |
| 15 millicuries as of 6/89. Current estimated activity is approximately 40 |
| microcuries of Cadmium-109." |
| |
| "The LICENSEE and the Agency continue to investigate this event." |
| |
| "The U.S. NRC and the U.S. FBI are being notified of this event." |
| |
| (Call the NRC Operations Officer for contact information.) |
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|General Information or Other |Event Number: 37494 |
+------------------------------------------------------------------------------+
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| REP ORG: WESTRONICS |NOTIFICATION DATE: 11/06/2000|
|LICENSEE: WESTRONICS |NOTIFICATION TIME: 14:05[EST]|
| CITY: KINGWOOD REGION: 4 |EVENT DATE: 11/03/2000|
| COUNTY: STATE: TX |EVENT TIME: 12:00[CST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 11/06/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOE TAPIA R4 |
| |BRIAN BONSER R2 |
+------------------------------------------------+VERN HODGE NRR |
| NRC NOTIFIED BY: ROBERT AGEE | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| WESTRONICS CSVC VIDEOGRAPHIC RECORDERS |
| |
| On or about November 3, 2000, Westronics determined that Westronics Series |
| CSVC "Smartview" Nuclear Safety Related videographic recorders, if utilized |
| to measure thermocouple inputs, require hardware modification to ensure |
| accurate measurement. The hardware modification requires installation of |
| capacitors associated with the Dallas 1620 Temperature Compensation Chips. |
| Instruments which would require the modification were shipped between July |
| 16, 1998 and July 7, 2000. Nuclear Power Plants affected are Riverbend, |
| Shearon Harris, and Brunswick. |
| |
| Westronics Corrective Action includes installation of the capacitors. |
| Affected Customers will be notified in accordance with the requirements of |
| 10CFR21. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37495 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MOUNTAINSIDE HOSPITAL |NOTIFICATION DATE: 11/06/2000|
|LICENSEE: NUCLETRON-OLD DELFT |NOTIFICATION TIME: 15:58[EST]|
| CITY: MONTCLAIR REGION: 1 |EVENT DATE: 07/14/1999|
| COUNTY: STATE: NJ |EVENT TIME: [EST]|
|LICENSE#: 29-03297-02 AGREEMENT: N |LAST UPDATE DATE: 11/06/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHELE EVANS R1 |
| |KEVIN RAMSEY NMSS |
+------------------------------------------------+BRIAN BONSER R2 |
| NRC NOTIFIED BY: ROBERT SASSO |GEOFFREY WRIGHT R3 |
| HQ OPS OFFICER: LEIGH TROCINE |JOE TAPIA R4 |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MOUNTAINSIDE HOSPITAL 10 CFR PART 21 REPORT OF A DEFECTIVE TRANSFER TUBE |
| THAT IS USED IN CONJUNCTION WITH A HIGH DOSE RATE BRACHYTHERAPY REMOTE |
| AFTERLOADER MANUFACTURED BY NUCLETRON-OLD DELFT |
| |
| The following text is a portion of a facsimile received from Mountainside |
| Hospital: |
| |
| "At the request Mr. David B. Everhart, who is conducting a field inspection |
| of our facility today, we are filing a report following the criteria of 10 |
| CFR [Part] 21, 'Reporting of Defects and Noncompliance.' " |
| |
| "3. The defective component was a transfer tube that is used in conjunction |
| with our High Dose Rate brachytherapy remote afterloader manufactured by: |
| Nucletron-Old Delft, [...]." |
| |
| "4. The defect involved separation of a metal connector end from the |
| transfer tube itself. It is unclear whether or not this would create a |
| safety hazard or simply prevent a treatment from being given. In our case, |
| there was no injury to either patients or staff because the failure did not |
| occur during patient treatment and the source was not in an exposed |
| position. Also, the tube itself was intact until removal from the head of |
| the unit was attempted." |
| |
| "5. The incident occurred on 7/14/99. A report of the defect was issued to |
| the FDA on 7/14/99, and a copy of the report sent to Nucletron on 7/15/99 |
| [...]." |
| |
| "6. The defective unit was immediately removed from service and sent to |
| Nucletron for analysis. All other transfer tubes were immediately checked |
| and found to be securely fastened to their connectors. Nucletron sent a |
| replacement transfer tube, and no other problems have transpired with any of |
| the transfer tubes since this incident." |
| |
| (Call the NRC operations officer for site contact information.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37496 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MOUNTAINSIDE HOSPITAL |NOTIFICATION DATE: 11/06/2000|
|LICENSEE: NUCLETRON-OLD DELFT |NOTIFICATION TIME: 15:58[EST]|
| CITY: MONTCLAIR REGION: 1 |EVENT DATE: 08/07/2000|
| COUNTY: STATE: NJ |EVENT TIME: [EST]|
|LICENSE#: 29-03297-02 AGREEMENT: N |LAST UPDATE DATE: 11/06/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHELE EVANS R1 |
| |KEVIN RAMSEY NMSS |
+------------------------------------------------+BRIAN BONSER R2 |
| NRC NOTIFIED BY: ROBERT SASSO |GEOFFREY WRIGHT R3 |
| HQ OPS OFFICER: LEIGH TROCINE |JOE TAPIA R4 |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MOUNTAINSIDE HOSPITAL 10 CFR PART 21 REPORT OF A DEFECTIVE TREATMENT HEAD OF |
| A MICROSELECTRON HIGH DOSE RATE (HDR) UNIT MANUFACTURED BY NUCLETRON-OLD |
| DELFT |
| |
| The following text is a portion of a facsimile received from Mountainside |
| Hospital: |
| |
| "At the request Mr. David B. Everhart, who is conducting a field inspection |
| of our facility today, we are filing a report following the criteria of 10 |
| CFR [PART] 21, 'Reporting of Defects and Noncompliance.' " |
| |
| "3. The defective component was the treatment head of our Microselectron HDR |
| Unit manufactured by Nucletron-Old Delft [...]." |
| |
| "4. The defect involved the failure of the treatment head to prevent the |
| check source and the HDR source from driving past the optical interlock when |
| no applicator was connected to the unit. The incident occurred during |
| machine warmup. There were no injuries to either patients or staff." |
| |
| "5. The incident occurred on 8/7/00. A service call was placed to Nucletron |
| [...]. Later that day, a service engineer from Nucletron visited our site. |
| The problem could not be reproduced [...] nor has it occurred any time |
| since." |
| |
| (Call the NRC operations officer for contact information.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37497 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 11/06/2000|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 17:07[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/06/2000|
+------------------------------------------------+EVENT TIME: 15:41[EST]|
| NRC NOTIFIED BY: PAUL UNDERWOOD |LAST UPDATE DATE: 11/06/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRIAN BONSER R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| GROUP II, PRIMARY CONTAINMENT ISOLATION VALVE (PCIV), ISOLATION FOLLOWING A |
| PLANNED MANUAL REACTOR SCRAM |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "A Group II PCIV isolation (setpoint +3.0 inches) occurred at 15:41 on |
| 11/06/00 following a planned manual reactor scram ([that occurred at] 1540 |
| on 11/06/00)." |
| |
| "Prior to the scram, reactor water level had been increased to approximately |
| 45 inches in anticipation of reactor water level decreasing following the |
| scram." |
| |
| "The planned reactor scram was part of a forced outage." |
| |
| "All valves functioned as required." |
| |
| The licensee stated that reactor water level momentarily decreased to the |
| Group II PCIV isolation setpoint following the reactor scram. The licensee |
| also stated that all systems functioned as required and that there was |
| nothing unusual or misunderstood. |
| |
| All rods fully inserted following the reactor scram. The Group II isolation |
| has been reset, and the PCIV valves have been returned to their original |
| positions. |
| |
| The NRC resident inspector was in the control room at the time of the event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37498 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 11/07/2000|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 05:30[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/07/2000|
+------------------------------------------------+EVENT TIME: 02:31[EST]|
| NRC NOTIFIED BY: PETE ORPHANOS |LAST UPDATE DATE: 11/07/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHELE EVANS R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
|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 Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) ISOLATED AND INOPERABLE DUE TO FAILED |
| STEAM LEAK DETECTION SYSTEM TEMPERATURE ELEMENT |
| |
| "On November 7, 2000 at 0231[EST] Limerick Generating Station received a |
| High Pressure Coolant Injection (HPCI) System isolation due to a failed |
| Steam Leak Detection System temperature element. Outboard isolation valves |
| HV-055-2F003, HV-055-2F100, HV-055-2F041 and HV-055-2F042 received isolation |
| commands. The system isolated as designed. Investigation [into] the cause |
| of the failed temperature element is ongoing. The HPCI system remains |
| isolated and inoperable." |
| |
| Unit 2 is in a 14-day LCO A/S. Other ECCS equipment has been verified |
| operable. The licensee informed the NRC resident inspector. |
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