Event Notification Report for July 9, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/08/2003 - 07/09/2003
** EVENT NUMBERS **
39975 39976 39982 39984 39985
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|General Information or Other |Event Number: 39975 |
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| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 07/03/2003|
|LICENSEE: H&G INSPECTION |NOTIFICATION TIME: 17:59[EDT]|
| CITY: Texas City REGION: 4 |EVENT DATE: 05/20/2003|
| COUNTY: STATE: TX |EVENT TIME: 14:30[CDT]|
|LICENSE#: L02181 AGREEMENT: Y |LAST UPDATE DATE: 07/03/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES MARSCHALL R4 |
| |THOMAS ESSIG NMSS |
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| NRC NOTIFIED BY: HELEN WATKINS | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
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| | |
| | |
| | |
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EVENT TEXT
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| OVEREXPOSURE |
| |
| Event occurred on May 20, 2003 between the hours of 0200 and 0230 hours CDT |
| at the Amoco Refinery in Texas City, TX. Overexposure was reported to the |
| Texas Dept. of Health on July 3, 2003. |
| |
| "A radiography source was not cranked into the fully shielded position |
| resulting in a 6.403 R whole body exposure to a radiographer. The |
| radiographer was making wall thickness exposures using a 100 curie cobalt 60 |
| source with a directional collimator. The radiographer made the last |
| exposure for the night, then proceeded to retrieve the film and take it for |
| development in the darkroom. The radiographer believed the pigtail had been |
| fully retracted, however, his initial survey was not conclusive because his |
| survey meter was not turned on. Although the ratemeter was alarming, |
| because of the noise level and the ear plugs, he did not initially hear |
| ratemeter alarming. When he did hear the faint ringing he checked the meter |
| and it was off. When the radiographer turned the meter on and resurveyed the |
| guide tubes, the needle went off-scale. He checked his pocket dosimeter and |
| it was off scale. The radiographer then retracted the pigtail into the |
| fully shielded position. The radiographers reported the event to their |
| management by telephone, then returned to the company shop. |
| |
| "The following day the personnel monitoring badge was sent for emergency |
| processing. The radiographer believes he was exposed for about one minute. |
| |
| "We will provide additional information as it is collected" |
| |
| Source Production & Equipment Company. |
| Source Information: |
| Model G-70 sn# C60-02 |
| 101 Curies cobalt-60 on May 29, 2002 (3737GBq) |
| |
| Texas Incident No: I-8033 |
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|General Information or Other |Event Number: 39976 |
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| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 07/03/2003|
|LICENSEE: SUNOCO CHEMICALS |NOTIFICATION TIME: 18:41[EDT]|
| CITY: LaPorte REGION: 4 |EVENT DATE: 06/19/2003|
| COUNTY: STATE: TX |EVENT TIME: 06:45[CDT]|
|LICENSE#: L02778 AGREEMENT: Y |LAST UPDATE DATE: 07/03/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES MARSCHALL R4 |
| |THOMAS ESSIG NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HELEN WATKINS | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| DAMAGED TEXAS NUCLEAR MODEL 5180A LEVEL GAUGE |
| |
| "An explosion and fire occurred in a distillation unit. The operating units |
| were shut down and the fire was extinguished. A visual inspection of a |
| level gauge installed on a vessel located in the area showed the device was |
| intact with no apparent physical damage except heat discoloration was |
| visible on the device. A preliminary survey found no readings above the |
| regulatory limits. However, an attempt to close the shutter was made and |
| debris and molten materials made the closing difficult. A wipe test was |
| performed with no leakage found. The device and area was barricaded to |
| prevent unauthorized entry. |
| |
| "Consultant Assistance: |
| A radiation technician from Alpha Process Sales inspected the device and the |
| area. Occupancy surveys were made and showed no persons who entered the |
| area received exposures over the allowable limits. |
| |
| "Thermo-Measuretech of Round Rock, TX, an authorized company, removed the |
| device and took possession for disposal. |
| |
| "TX Nuclear Level Gauge |
| TN model 5180A |
| source sn# B380, 500mCi [millicuries] Cs-137" |
| |
| Texas Incident No: I-8032 |
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|Power Reactor |Event Number: 39982 |
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| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 07/08/2003|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 02:52[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 07/07/2003|
+------------------------------------------------+EVENT TIME: 23:19[CDT]|
| NRC NOTIFIED BY: LARRY BLUNK |LAST UPDATE DATE: 07/08/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHRIS MILLER R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR SCRAM AT LaSALLE UNIT 2 DUE TO TRIP OF THE MAIN TURBINE |
| |
| "At 2319 CDT on July 7, 2003 LaSalle Unit 2 Automatically scrammed due to a |
| trip of the main turbine. The main turbine trip was caused by a main |
| generator lockout due to a fault on the "B" phase of the main power |
| disconnect. All rods inserted on the scram. Three safety relief valves |
| actuated in the relief mode on the turbine trip. Both reactor recirc pumps |
| tripped off and all three circulation water pumps tripped off. The main |
| steam line isolation valves and main steam line drains were closed due to |
| the loss of the circulating water pumps. Tech Spec 3.0.3 was entered due to |
| simultaneous inoperability of A, B, and C residual heat removal pumps. "A" |
| residual heat removal pump was declared inoperable due to use in suppression |
| pool cooling. "B" and "C" residual heat removal pumps were inoperable at the |
| beginning of the event for planned [preventive] maintenance on the essential |
| core cooling system ventilation. There were no automatic actuations of ECCS |
| systems and no primary or secondary containment isolation system actuations. |
| There [were] no ECCS injections into the reactor vessel. There were 3 |
| subsequent auto scram signals on low reactor level due to level shrink on |
| SRV closure in pressure control." |
| |
| Unit 2 is currently stable with reactor feedwater being provided by the |
| condensate system and reactor heat removal using SRV steam discharge to the |
| suppression pool. Residual heat removal pumps "A" and "B" are operating to |
| provide suppression pool cooling. "C" residual heat removal pump has been |
| returned to operable status. All emergency diesel generators are available. |
| |
| The licensee also reported that the electrical system transient resulted in |
| the need to reduce power on LaSalle Unit 1 from 100% to ~92% to stabilize |
| condensate booster pump suction pressure. |
| |
| The licensee has notified the NRC Resident Inspector |
| |
| * * * UPDATE ON 7/8/03 AT 1108 EDT FROM DANIEL COVEYOU TO GERRY WAIG * * * |
| |
| "At 0306 [CDT] on 7/8/03 there was an automatic RPS [Reactor Protection |
| System] actuation due to reactor water level 3. At the time of the scram all |
| control rods were already fully inserted. There was no rod movement as a |
| result of the 0306 [CDT] auto reactor scram. The low level condition was a |
| momentary response due to level shrink upon safety relief valve closure. The |
| safety relief valves were being manually operated to control reactor |
| pressure." |
| |
| The licensee has notified the NRC Resident Inspector. |
| |
| Notified R3DO ( Chris Miller) |
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|Power Reactor |Event Number: 39984 |
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| FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 07/08/2003|
| UNIT: [2] [] [] STATE: SC |NOTIFICATION TIME: 16:42[EDT]|
| RXTYPE: [2] W-3-LP |EVENT DATE: 07/08/2003|
+------------------------------------------------+EVENT TIME: 10:58[EDT]|
| NRC NOTIFIED BY: CHUCK BAUCOM |LAST UPDATE DATE: 07/08/2003|
| HQ OPS OFFICER: ERIC THOMAS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |THOMAS DECKER R2 |
|10 CFR SECTION: | |
|ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| LOSS OF COMMUNICATIONS CAPABILITY |
| |
| "At approximately 10:58 hours (EDT) on July 8, 2003, a fiber optic cable |
| that provides service to H. B. Robinson Steam Electric Plant (HBRSEP), Unit |
| No. 2, was removed from service due to highway bridge repairs on State Road |
| 23, Old Camden Road, approximately 1.5 miles west of the plant site. This |
| resulted in the loss of circuits supported by Bellsouth, which includes the |
| selective signaling system for communication with the state and counties, an |
| additional phone system for internal and external communication called ESSX, |
| the NRC T1 link, and dial 9 service from the internal plant telephone |
| system. Communications capability remained available via the on-site PBX |
| telephone service, cellular phone service, satellite phone, and the Progress |
| Energy Voicenet system. |
| |
| "At approximately 09:00 hours [EDT], Bellsouth personnel informed HBRSEP, |
| Unit No. 2, personnel of the plan to temporarily remove the cable from |
| service at approximately 11:00 hours [EDT] in support of the bridge repair |
| work. HBRSEP, Unit No. 2, Emergency Preparedness personnel notified the |
| control room Superintendent of Shift Operations pertaining to the impending |
| communications outage and verified that a cellular phone and satellite phone |
| were available in the control room. The state and county emergency operation |
| centers, warning points, and back-up warning points were notified of the |
| planned communications link outage prior to its removal from service. The |
| fiber optic cable was placed back in service at approximately 14:51 hours |
| [EDT] and the systems were subsequently tested satisfactorily. |
| |
| "This report is being made in accordance with 10 CFR 50.72(b)(3)(xiii), |
| which is any event that results in a major loss of offsite communications |
| capability. The capability to provide notification as required was |
| maintained by use of alternate systems, specifically cellular phone, |
| satellite phone, and the Progress Energy Voicenet system. The resident |
| inspector has been notified." |
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|Power Reactor |Event Number: 39985 |
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| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 07/09/2003|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 03:05[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/09/2003|
+------------------------------------------------+EVENT TIME: 01:09[CDT]|
| NRC NOTIFIED BY: LES MILLER |LAST UPDATE DATE: 07/09/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |KRISS KENNEDY R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 99 Power Operation |0 Hot Standby |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR TRIP DUE TO REACTOR COOLANT PUMP BREAKER OPENING WITH |
| INITIATION OF AUXILIARY FEEDWATER SYSTEM AFTER THE TRIP |
| |
| "At 0109 hrs. CDT, Unit 2 reactor tripped due to opening of RCP [Reactor |
| Coolant Pump] 2-04 breaker resulting in "Rx >48% 1/4 loop flow low trip". |
| Cause of the breaker opening is unknown and under investigation. All |
| systems responded as required. Auxiliary Feed Water auto-start occurred due |
| to steam generator shrink, both motor driver AFW pumps and Turbine Driven |
| AFW pump started (ESF)." |
| |
| All rods inserted into the core during the trip. The electrical grid is |
| stable. There were no power-operated or manual relief valve lifts during |
| the transient. The other unit was not affected by the transient. Decay |
| heat is being removed via steam generator blowdown and AFW. The plant is |
| maintaining at NOP/NOT in mode 3 until the cause of the breaker trip is |
| known and repaired. Pressurizer pressure control is in automatic. There is |
| no identified primary-to-secondary leakage. |
| |
| The licensee has informed the NRC Resident Inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021