Event Notification Report for October 19, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/18/2000 - 10/19/2000
** EVENT NUMBERS **
37354 37429 37435 37436 37437 37438 37439
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|General Information or Other |Event Number: 37354 |
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| REP ORG: SCIENTECH/NUSI |NOTIFICATION DATE: 09/20/2000|
|LICENSEE: SCIENTECH/NUSI |NOTIFICATION TIME: 07:42[EDT]|
| CITY: GAITHERSBURG REGION: 1 |EVENT DATE: 09/14/2000|
| COUNTY: STATE: MD |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 10/18/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM RULAND R1 |
| |VERN HODGE NRR |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BOOSKA | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| PART 21 RELATED TO DEFECTS IN DELTA T TIME DOMAIN MODULES SUPPLIED TO GINNA |
| STATION |
| |
| SCIENTECH Inc.'s subsidiary NUS Instruments, Inc. (NUSI) has determined that |
| a Basic Component, supplied to Rochester Gas & Electric Ginna Station |
| Nuclear Plant under RG&E purchase order NQ-l5877-A-JW, may contain a defect |
| that is reportable under 10CFR21. NUSI became aware of this potential |
| defect September 14, 2000. SCIENTECH, Inc. President was informed September |
| 19, 2000. RG&E is aware of this problem and the affected components have |
| been modified to remove any undesirable effects on their systems. A formal |
| written report will be provided within 30 days of this notification. The |
| components, DELTA T Time Domain Modules, M/N: TMD500-08/08/08/08-15-08-01/2, |
| P/N: MBA-E062PA-l, Rev. 0 (4 ea.), were manufactured by NUSI. These |
| components have been supplied to no other utility for use in Safety Related |
| Systems. NUSI has opened a 10CFR21 file concerning this component and has |
| numbered it as 21-00-01. |
| |
| * * * UPDATE 1343EDT on 10/18/00 from Marty Booska to S. Sandin * * * |
| |
| The licensee submitted a formal copy of the Part 21 via fax with a hard copy |
| being sent by mail tomorrow. Notified R1DO(Cook) and NRR(Vern Hodge) via |
| fax. |
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|Power Reactor |Event Number: 37429 |
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| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 10/14/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 05:14[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/14/2000|
+------------------------------------------------+EVENT TIME: 03:24[CDT]|
| NRC NOTIFIED BY: WILLIAM GREEN |LAST UPDATE DATE: 10/18/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVE LOVELESS R4 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR SCRAM DUE TO A MAIN GENERATOR TRIP FOR UNKNOWN REASONS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 0324 [CDT], a reactor scram occurred due to a main generator trip. |
| Group isolations 2, 3[, and] 6 occurred due to low reactor water level. The |
| lowest [reactor water] level recorded was -20 inches on [the] wide range |
| level recorder. Reactor water level recovered, and both reactor [feedwater] |
| pumps tripped on high reactor water level. Group isolations have been |
| verified and reset. [The] 'A' reactor [feedwater] pump has been returned to |
| service and is being used to control water level. [High pressure coolant |
| injection] and [reactor core isolation cooling] did not inject and were not |
| needed to control reactor water level. The plant will be placed in Cold |
| Shutdown. The electrical grid is stable." |
| |
| The licensee stated that all control rods fully inserted and that all |
| systems functioned as required. The licensee also stated that alternate rod |
| insertion initiated as a result of high pressure due to the transient. The |
| highest pressure observed was 1,085 psi. None of the relief valves lifted, |
| and the main steam isolation valves remained open throughout the event. |
| Steam is currently being dumped to the condenser. |
| |
| In addition, the licensee stated that the cause of the main generator trip |
| is currently under investigation. There were no related surveillance or |
| maintenance activities ongoing at the time of the event. |
| |
| The licensee notified the NRC resident inspector. |
| |
| * * * UPDATE on 10/18/00 at 0428 ET by Myers taken by MacKinnon * * * |
| |
| A detailed review of the plant response to the scram has been conducted. |
| This review indicated the following clarification to the initial report are |
| needed: |
| |
| Alternate Rod Insertion initiated on low level, rather than high pressure. |
| The low level was not in long enough to trip the Recirculation pumps. The |
| pumps trip after a 9 second delay, and the low level signal was only in for |
| ~ 7 seconds. |
| |
| Initial indications were that reactor pressure had reached 1085 psig, based |
| on pressure recorder LRPR97, the highest reading of the pressure recorders. |
| Additional pressure recorders and the plant computer indicate pressure |
| reached a maximum of ~ 1068 psig. Evaluation of the recorder indicates it |
| is in calibration, and the "overshoot" of indicated pressure is due to |
| mechanical characteristics of the recorder linkage. NRC R4DO (John Pellet) |
| notified. |
| |
| The NRC Resident Inspector was informed of this update by the licensee. |
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|Power Reactor |Event Number: 37435 |
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| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 10/18/2000|
| UNIT: [] [2] [] STATE: FL |NOTIFICATION TIME: 12:00[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 10/18/2000|
+------------------------------------------------+EVENT TIME: 10:52[EDT]|
| NRC NOTIFIED BY: ALAN T. HALL |LAST UPDATE DATE: 10/18/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| OFFSITE NOTIFICATION TO LOCAL FIRE DEPARTMENT FOR FIRE ON OWNER CONTROLLED |
| POPERTY |
| |
| "REFERENCE NUREG [1022 - SECTION] 3.3.7: |
| |
| NOTIFICATION OF CONTACT OF ST. LUCIE '911' (FIRE) TO REQUEST OFFSITE FIRE |
| DEPARTMENT TO EXTINGUISH A SMALL GRASS FIRE EAST OF PLANT BETWEEN DUNE LINE |
| AND MANGROVES, IN A GRASS COVERED PARKING AREA. TOTAL TIME FROM DISCOVERY |
| UNTIL NOTIFICATION OF 'FIRE IS OUT' WAS 38 MINUTES. NO E-PLAN ACTIVATION |
| WAS REQUIRED. FIRE [WAS] NOT ON PLANT SITE." |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND LOCAL AUTHORITIES. |
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|Power Reactor |Event Number: 37436 |
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| FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 10/18/2000|
| UNIT: [1] [2] [] STATE: TN |NOTIFICATION TIME: 13:47[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/18/2000|
+------------------------------------------------+EVENT TIME: 12:00[EDT]|
| NRC NOTIFIED BY: TOM RYAN |LAST UPDATE DATE: 10/18/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N Y 78 Power Operation |78 Power Operation |
| | |
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EVENT TEXT
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| OFFSITE AGENCIES NOTIFIED OF INADVERTENT ACTUATION OF OFFSITE SIRENS DURING |
| "SILENT TEST" |
| |
| "At approximately, 1200 on 10/18/2000, the Prompt Notification System (PNS) |
| sirens were inadvertently actuated during a 'Silent Test' of the PNS system |
| by the Hamilton County Emergency Management Agency (HCEMA). The Corporate |
| Emergency Planning (EP) personnel were in contact with the HCEMA and |
| Tennessee Emergency Management Agency (TEMA) Staff at the time of the test |
| and immediately canceled the activation of PNS system at approximately 1201. |
| The Corporate Operations Duty Specialist (ODS) notified the Sequoyah |
| Operations Shift Manager at approximately 1205. Tennessee Valley Authority |
| (TVA) Public Information personnel notified the media. Due to heightened |
| public and media interest and notifications, this incident is being reported |
| under 10CFR 50.72(b)(2)(vi)." |
| |
| The licensee informed state/local agencies, local media and the NRC resident |
| inspector. |
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|Power Reactor |Event Number: 37437 |
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| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 10/18/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 15:04[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/18/2000|
+------------------------------------------------+EVENT TIME: 14:00[EDT]|
| NRC NOTIFIED BY: JOSEPH KLEVORN |LAST UPDATE DATE: 10/18/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM COOK R1 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| LICENSEE IDENTIFIED DURING SURVEILLANCE TESTING THAT THE CONTAINMENT LEAK |
| RATE EXCEEDS THE ALLOWABLE LEAK RATE |
| |
| "PRIMARY CONTAINMENT AS-FOUND MINIMUM PATHWAY LEAK RATE EXCEEDED THE |
| ALLOWABLE LEAK RATE OF 1.5%/DAY DURING REFUELING OUTAGE 14. THE MAJOR |
| CONTRIBUTOR TO TOTAL CONTAINMENT LEAKAGE WAS THE 'D' MAIN STEAM LINE WHOSE |
| LEAK RATE WAS NOT ABLE TO BE QUANTIFIED." |
| |
| THE LICENSEE HAS APPROXIMATELY 35 ADDITIONAL COMPONENTS TO EVALUATE PRIOR TO |
| COMPLETING LEAK RATE TESTING. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
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|General Information or Other |Event Number: 37438 |
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| REP ORG: MARYLAND DEPT OF THE ENVIRONMENT |NOTIFICATION DATE: 10/18/2000|
|LICENSEE: UNIVERSITY OF MARYLAND |NOTIFICATION TIME: 16:15[EDT]|
| CITY: REGION: 1 |EVENT DATE: 10/17/2000|
| COUNTY: STATE: MD |EVENT TIME: 19:00[EDT]|
|LICENSE#: MD-0701401 AGREEMENT: Y |LAST UPDATE DATE: 10/18/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |WILLIAM COOK R1 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RAY MANLEY | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| AGREEMENT STATE REPORT INVOLVING A MEDICAL MISADMINISTRATION (UNDERDOSE) |
| |
| AT 1650EDT ON 10/17/00, A 31 YEAR OLD MALE PATIENT UNDERGOING TREATMENT FOR |
| LIVER CANCER RECEIVED 23.4% OF THE PRESCRIBED 150 GRAY DOSE USING YTTRIUM-90 |
| GLASS SPHERES PRODUCED BY NORDION. THE LICENSEE HAS PERFORMED 10 SUCCESSFUL |
| THERAPIES OF THIS TYPE IN THE PAST. THE MANUFACTURER IS EVALUATING THE |
| ENTIRE DELIVERY SYSTEM IN ORDER TO DETERMINE ROOT CAUSE. THE LICENSEE'S |
| PRELIMINARY EVALUATION INDICATES A DIFFICULTY IN THE DELIVERY RESULTING FROM |
| AN AIR LEAK IN THE RUBBER CAP OF THE SOURCE VIAL AT THE SITE OF THE NEEDLE |
| INSERTION. THE LICENSEE SUSPECTS THAT THE INLET NEEDLE AND THE OUTLET |
| NEEDLE MAY HAVE BEEN INSERTED TOO CLOSE WHICH CAUSED THE RUBBER CAP TO LOSE |
| ITS SELF-SEAL CAPABILITY. AT 1900EDT ON 10/18, THE LICENSEE DETERMINED THAT |
| THE UNDERDOSE MET THE REPORTING REQUIREMENTS AS A MEDICAL MISADMINISTRATION. |
| |
| |
| THE STATE OF MARYLAND INTENDS TO CONDUCT AN INVESTIGATION OF THIS INCIDENT. |
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|Power Reactor |Event Number: 37439 |
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| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 10/18/2000|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 18:45[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 10/18/2000|
+------------------------------------------------+EVENT TIME: 14:37[CDT]|
| NRC NOTIFIED BY: TOM LYNCH |LAST UPDATE DATE: 10/18/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN PELLET R4 |
|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 99 Power Operation |99 Power Operation |
| | |
| | |
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EVENT TEXT
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| UNIT EXPERIENCED A MOMENTARY GRID DISTURBANCE RENDERING SEVERAL |
| SAFETY-RELATED RADIATION MONITORS INOPERABLE |
| |
| "At 1437CDT on 10/18/00, River Bend Station experienced an electrical |
| perturbation in the Baton Rouge area. Line 758 [138 kV] was lost which |
| feeds a local refinery and this loss resulted in a momentary grid |
| undervoltage condition. This undervoltage condition lasted less than one |
| (1) second. As a result of this undervoltage condition, power to selected |
| radiation monitor sample pumps was lost. Specifically, the Control Room |
| Fresh air intake radiation monitors on both Division I and Division II lost |
| sample pump power and this resulted in these monitors being inoperable for |
| approximately three (3) minutes. The monitors were subsequently restarted. |
| As a result of this condition, the radiation monitors would have been unable |
| to initiate the Control Room Fresh Air Filter trains upon receipt of a high |
| radiation signal. This signal is required to be operable when handling |
| irradiated fuel; modes 1, 2, 3 and/or performing operations with the |
| potential to drain the reactor vessel. No fuel handling or reactor vessel |
| drain activities were in progress. This condition also existed for the Fuel |
| Building ventilation radiation monitors. This condition is conservatively |
| being reported as a loss of safety function for the Control Room Fresh Air |
| System. Further evaluation if this condition is in progress." |
| |
| The licensee informed the NRC resident inspector. |
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