Event Notification Report for July 9, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/08/2002 - 07/09/2002
** EVENT NUMBERS **
38992 39021 39040 39045 39047
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 38992 |
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| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 06/14/2002|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 11:24[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 06/13/2002|
+------------------------------------------------+EVENT TIME: 11:30[EDT]|
| NRC NOTIFIED BY: DOUG RICHARDSON |LAST UPDATE DATE: 07/08/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LAWRENCE DOERFLEIN R1 |
|10 CFR SECTION: |JOHN DAVIDSON IAT |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| 24 HOUR REPORT ON LICENSE CONDITION 2F |
| |
| " At 1130 hours on 6/13/02 it was discovered that the Safety Relief Valve |
| (SRV) Position Indication Channel for one of the SRVs controlled from the |
| Remote Shutdown Panel was inoperable. The inoperability was due to both |
| alarm card inhibit switches for associated acoustic monitoring channel being |
| found to be in the inhibit position. These switches are normally in the |
| "alarm" position. With the switches in the "inhibit" position the SRV |
| position indication from a high vibration condition would not provide an |
| open position indication for the SRV in the Control Room or at the Remote |
| Shutdown Panel. Immediate Action was to return the switches to the alarm |
| position and all other SRV acoustic monitoring switches were verified to be |
| in the correct "alarm" position. |
| |
| "Technical Specification LCO 3.3.3.2 requires that the Remote Shutdown |
| System Functions shall be OPERABLE. With this channel inoperable, Required |
| Actions require restoration to OPERABLE status within 30 days OR placing the |
| Unit in Mode 3 within the following 12 hours. Since the potential exists |
| that this condition has existed in excess of the 30-day requirement this |
| event may be considered a Condition Prohibited by Technical Specifications. |
| |
| "This report is being made in accordance with Section 2F of Operating |
| License NPF-69 for Nine-Mile Point Unit 2. Section 2F requires that the |
| initial notification of a violation of any requirement contained in Section |
| 2C to the Operating License (License Conditions) be reported to the NRC |
| Operations Center via the Emergency Notification System within 24 hours with |
| written follow-up with 30 days. License Condition 2C requires that Nine Mile |
| Point Nuclear Station, LLC shall operate the facility in accordance with the |
| Technical Specifications." |
| |
| The NRC Resident Inspector has been notified. |
| |
| ****Retraction on 07/08/02 at 1634 ET by Mr. Cigler taken by MacKinnon **** |
| |
| |
| "A subsequent investigation concluded that there is no firm evidence that |
| the switches were in the wrong position in excess of 30 days. Based on the |
| guidance of NUREG 1022, Rev 2, section 3.2.2, the previous report made is |
| being retracted." R1DO (Brian McDermott) |
| |
| The NRC Resident Inspector was notified of this retraction by the licensee. |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39021 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 06/27/2002|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 06:45[EDT]|
| RXTYPE: [1] GE-2 |EVENT DATE: 06/26/2002|
+------------------------------------------------+EVENT TIME: 22:52[EDT]|
| NRC NOTIFIED BY: ERIC DEMONCH |LAST UPDATE DATE: 07/08/2002|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MICHAEL MODES R1 |
|10 CFR SECTION: | |
|AINC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| BOTH CHANNELS OF OFFGAS RADIATION MONITORS DECLARED INOPERABLE
|
| |
| Both channels of offgas radiation monitors declared inoperable due to a |
| common mode failure. Both channels detect offgas radiation levels in the |
| same sample volume. The sample volume filled with condensate suppressing |
| the radiation levels. The offgas radiation monitors provide for isolation |
| of the main condensers on indications of fuel element failure. This puts |
| the licensee in a 72 hour clock allowing for repairs or shutdown, per |
| Technical Specification Table 3.1.1 Instrument Operability. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
| |
| * * * RETRACTED AT 1412 EDT ON 7/8/02 BY STEVE FULLER TO FANGIE JONES * * * |
| |
| The licensee is retracting the event notification after reviewing the event |
| and determining that the monitors do not perform a safety function that is |
| relied on in the safety analysis of the plant. Also, the monitors do not |
| affect the plant or its safety barriers. |
| |
| The licensee intends to notify the NRC Resident Inspector. The R1DO (Brian |
| McDermott) |
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+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39040 |
+------------------------------------------------------------------------------+
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| REP ORG: COLORADO DEPT OF HEALTH |NOTIFICATION DATE: 07/03/2002|
|LICENSEE: SWEDISH MEDICAL CENTER |NOTIFICATION TIME: 12:09[EDT]|
| CITY: DENVER REGION: 4 |EVENT DATE: 06/24/2002|
| COUNTY: STATE: CO |EVENT TIME: [MDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 07/03/2002|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DALE POWERS R4 |
| | NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: STATE OF COLORADO | |
| HQ OPS OFFICER: GERRY WAIG | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION |
| |
| The following is taken, in-part, from a facsimile report: |
| |
| "A patient received 5 fractions of brachytberapy using an lr-192 HDR unit |
| and a tandem/ovoids applicator. During the treatment planning process, an |
| incorrect magnification factor for the orthogonal films on which the |
| Dosimetry was based had been used. This resulted in an underdose of |
| approximately 50% or more depending on the part of the treatment volume used |
| for comparison. |
| |
| "The initial and corrected dosimetry has been reviewed by 3 additional |
| physicists. The corrected Dosimetry has been verified using an independent |
| film digitization system and TPS. A composite Dosimetry summary of the |
| treatment as delivered has been prepared and verified. Based on that |
| information the prescribing physician will administer an additional |
| brachytherapy application to compensate for the lower than prescribed dose |
| from the initial 5 fractions. |
| |
| [The original prescribing physician] "contacted the patient tonight, 2 July |
| 2002. He reported the underdose, recommended an additional brachytherapy |
| procedure and described the misadministration report." |
+------------------------------------------------------------------------------+
.
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39045 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 07/08/2002|
| UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 02:57[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/07/2002|
+------------------------------------------------+EVENT TIME: 23:12[CDT]|
| NRC NOTIFIED BY: STEVEN KASPER |LAST UPDATE DATE: 07/08/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DALE POWERS 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 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP |
| |
| "At 2312 on 07/07/2002 Unit 2 Reactor automatically tripped from full power |
| due to a high high Steam Generator Level In the 2B Steam Generator. Prior to |
| the trip Vital distribution panel 1202 lost power when it's normal power |
| supply inverter failed. All of the controlling channels of Steam Generator |
| level were powered from this distribution panel and failed low on the loss |
| of power. Operators were in the process of taking manual control of all Feed |
| Water Regulating valves when the Main Turbine trip was actuated due to the |
| high high level in Steam Generator 28. A Reactor Trip occurred due to |
| Turbine Trip above 50% power. The unit is stable in Mode 3 with RCS |
| temperature at 567 degrees Fahrenheit, and RCS pressure of 2235 pslg. |
| |
| "We also make the following report per 10CFR50.72(b)(3)(iv): Following the |
| Reactor Trip the Auxiliary Feed Water System automatically actuated on low |
| Steam Generator level. This is normal for a trip in Unit 2 from full power |
| with the Model E Steam Generators. |
| |
| "The following information is also provided: |
| |
| "Did the control rods fully insert? Yes |
| |
| "Did steam bypass to the condenser or to atmosphere? The Steam Dump system |
| automatically operated to maintain temperature. No steam bypass to |
| atmosphere occurred. |
| |
| "Did any primary/secondary relief valve lift? NO |
| |
| "Any significant TS LCOs entered? TS 3.8.3.1 Action b. was entered due to |
| vital DP 1202 not being powered from its normal power supply inverter. We |
| must reenergize the AC distribution panel from its associated inverter |
| connected to its associated D.C. bus within 24 hours or be in at least HOT |
| Standby within the next 6 hours and in Cold Shutdown within the following 30 |
| hours. |
| |
| "Item not understood: Channel 1 of P-13 Reactor Trip System interlock status |
| light is currently blinking. This condition must be understood and corrected |
| prior to restart." |
| |
| The NRC resident inspector was notified. |
+------------------------------------------------------------------------------+
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39047 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 07/08/2002|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 16:42[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 07/08/2002|
+------------------------------------------------+EVENT TIME: 16:00[EDT]|
| NRC NOTIFIED BY: BARRETT NICHOLS |LAST UPDATE DATE: 07/08/2002|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRIAN MCDERMOTT R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO STATE OF THE CONNECTICUT DEPARTMENT OF
ENVIRONMENTAL |
| PROTECTION |
| |
| In a Material Engineering Lab storage cabinet a 250 milliliter container |
| approximately 25% full was found to contain liquid picric acid. The |
| Material Engineering Lab is located in a Warehouse in the Owners Control |
| Area but is not in the Protected Area. A contract HAZMAT team, Onyx, was |
| called to the site to remove the container. The State of Connecticut |
| Department of Environmental Protection was notified of this information. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021