Event Notification Report for February 19, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/14/2003 - 02/19/2003
** EVENT NUMBERS **
39585 39586 39587 39588 39589 39590 39591 39592 39593 39595
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39585 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: IOWA DEPARTMENT OF PUBLIC HEALTH |NOTIFICATION DATE: 02/14/2003|
|LICENSEE: UNIVERSITY OF IOWA |NOTIFICATION TIME: 11:22[EST]|
| CITY: IOWA CITY REGION: 3 |EVENT DATE: 02/06/2003|
| COUNTY: STATE: IA |EVENT TIME: [CST]|
|LICENSE#: 0037-1-52-AAB AGREEMENT: Y |LAST UPDATE DATE: 02/14/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |SONIA BURGESS R3 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: GEORGE JOHNS | |
| HQ OPS OFFICER: MIKE RIPLEY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - MEDICAL EVENT |
| |
| The Iowa Department of Public Health provided the following via fax: |
| |
| "Here is a summary of the event that occurred a week ago: |
| |
| "The University of Iowa (Iowa Radioactive Materials License No. 0037-1 |
| -52-AAB) provided a 700 Rad (7 Gy [Gray]) dose to an unintended site using a |
| Varian-TEM Ltd. Model VariSource HDR Remote Afterloader. The planned area |
| of treatment was a tumor in the bronchial area. |
| |
| "The licensee measured and tested a catheter using the dummy source. After |
| the test, the catheter was placed in a box and sent for sterilization. On |
| February 6, 2003. the licensee used what they thought was the correct |
| catheter during one fraction. |
| |
| "When the patient returned on February 13, 2002, for the second fraction, a |
| medical physicist discovered that the catheter was 30 centimeters too |
| short. |
| |
| "The dose was delivered to the skin in the nasal passages rather than the |
| bronchial area. The attending physician was present at the time the error |
| was discovered and has been informed. The patient has been advised of the |
| error and given the option of discontinuing treatment. The patient has |
| elected to undergo treatment for the correct site. |
| |
| "The cause of the error is currently under investigation and the licensee's |
| report, which is due to IDPH by February 28, 2003, will address corrective |
| actions." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 39586 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: DEPARTMENT OF VETERANS AFFAIRS |NOTIFICATION DATE: 02/14/2003|
|LICENSEE: PHILADELPHIA VA MEDICAL CENTER |NOTIFICATION TIME: 14:32[EST]|
| CITY: PHILADELPHIA REGION: 1 |EVENT DATE: 02/03/2003|
| COUNTY: STATE: PA |EVENT TIME: [EST]|
|LICENSE#: 37-00062-07 AGREEMENT: N |LAST UPDATE DATE: 02/14/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GLENN MEYER R1 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: PAUL YURKO | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|LOTH 35.3045(a)(3) DOSE TO OTHER SITE > SP| |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POSSIBLE MEDICAL EVENT AT PHILADELPHIA VETERANS ADMINISTRATION MEDICAL |
| CENTER |
| |
| Informed by a representative of the Department of Veteran's Affairs National |
| Health Physics Program (NHPP) that a possible medical event may have |
| occurred at the Philadelphia Veterans Administration Medical Center. The |
| event took place on February 3, 2003 but was not determined until it was |
| discussed on February 13, 2003. |
| |
| The procedure being performed at the time of the event was a permanent |
| prostate seed implant brachytherapy. The nuclide involved is I-125. A |
| fraction of the seeds intended to be implanted into the prostate were |
| recovered from the bladder. The medical authorized user (the physician |
| prescribing and performing the procedure) rewrote the written directive in |
| the operating room to reflect the number of seeds that were successfully |
| implanted into the prostate. Calculations are presently being made to |
| determine the exposure to the bladder. Preliminary calculations indicate |
| that there are no deterministic effects to the patient as a result of the |
| event. All the seeds are presently accounted for. There was no patient |
| intervention. The NHPP is currently investigating the event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39587 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: STATE OF CALIFORNIA |NOTIFICATION DATE: 02/14/2003|
|LICENSEE: UNIVERSITY OF CALIFORNIA AT SAN DIEGO|NOTIFICATION TIME: 16:55[EST]|
| CITY: SAN DIEGO REGION: 4 |EVENT DATE: 02/13/2003|
| COUNTY: SAN DIEGO STATE: CA |EVENT TIME: 07:30[PST]|
|LICENSE#: 1339-37 AGREEMENT: Y |LAST UPDATE DATE: 02/14/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES MARSCHALL R4 |
| |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BARBARA HAMRICK | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT- UNIVERSITY OF CALIFORNIA AT SAN DIEGO SAFETY |
| EQUIPMENT FAILS TO FUNCTION |
| |
| The following information was obtained via e-mail from California Department |
| of Health Services, Radiological Health Branch: |
| |
| "At approximately 7:30 am [PST], February 13, 2003, the University of |
| California at San Diego (California Radioactive Materials No. 1339-37) was |
| performing one of the monthly Quality Assurance (QA) tests on their High |
| Dose Rate Afterloader (HDRA). They had a treatment scheduled for later that |
| morning, and the guide tubes and extenders were already attached in |
| preparation for the treatment. During the typical monthly check, the |
| licensee disconnects two of the guide tubes, and attaches the QA catheter, |
| placing one end in the well chamber to measure the source strength, and that |
| is what occurred this time. However, when the channel was set to run the QA |
| test, the operator inadvertently set the wrong channel, and the source was |
| extended into one of the guide tubes, rather than through the QA catheter |
| and into the well chamber. When the operator tried to retract the source, |
| it would not retract. |
| |
| "The operator used a survey meter at the door of the treatment room to |
| verify the source was still out, and re-confirmed that with the indication |
| on the room monitor. After several attempts to retract the source from the |
| console, the operator entered the room, and placed all the guide tubes into |
| the emergency source pig, and closed the lid. The operator states the |
| dose-rate in the room, with the source in the pig was reduced to |
| approximately 3 milliR/hr at one foot from the pig. He estimates he was |
| within one meter of the unshielded source for no more than 5 seconds, and |
| that his hand was within one foot of the source for approximately 3 seconds. |
| Currently, the licensee estimates the dose to the operator as under 100 |
| millirem whole body. They have sent his dosimeter for emergency processing. |
| It is unknown at this time if he was wearing an extremity dosimeter. |
| |
| "After placing the guide tubes with the source in the pig, the operator left |
| the room, locked it, and contacted Nucletron Corporation to service the |
| device. The licensee contacted the State of California with this |
| information at approximately 10:30 am PST on February 14, 2003. The State |
| of California is investigating this event, and will provide updated |
| information as needed. This event would be reportable to the NRC pursuant |
| to 10 CFR 30.50(b)(2), and to the State of California under the comparable |
| California regulation (17 CCR 30295)." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 39588 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/15/2003|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:15[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/14/2003|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:00[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/15/2003|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |SONIA BURGESS R3 |
| DOCKET: 0707001 |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: STEVEN SKAGGS | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CRITICALITY CONTROL 24-HOUR (BULLETIN 91-01) REPORT |
| |
| The following information was obtained from the regulatee via facsimile: |
| |
| "At 1900 on 2-14-03, the Plant Shift Superintendent (PSS) was notified that |
| the C-333 "E" Surge Drum, 0-25 psia pressure recorder was not working and |
| the 0-2 pressure recorder was off-scale. The 0-25 psia pressure recorder |
| had failed violating the requirements of a Safety Related Item (SRI) |
| credited in NCSE [Nuclear Criticality Safety Evaluation] 016. As a result, |
| the shiftly pressure checks could not be performed. Instead of installing a |
| sample buggy to measure pressure, the drum pressure was reduced in order to |
| read the pressure on the 0-2 [psia] pressure chart recorder. The purpose of |
| the pressure check is to identify if wet air in-leakage has begun on the |
| surge drum bank. |
| |
| "Double contingency has been restored since the ability to read pressure in |
| the surge drum bank using a properly operating AQ-NCS [Augmented Quality - |
| Nuclear Criticality Safety] pressure instrument has been restored. |
| |
| "The NRC Resident Inspector has been notified of this event. |
| |
| "SAFETY SIGNIFICANCE OF EVENTS: |
| |
| "Although pressure readings could not be taken due to a failed AQ-NCS |
| pressure instrument, there are several important mitigating factors. First, |
| the integrity of the drum bank has been maintained. Second, the uranium has |
| been maintained in the gas phase. |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW |
| CRITICALITY COULD OCCUR) |
| |
| "These drums are used to store gasses. Therefore, in order for a criticality |
| to be possible, wet air would have to react with any UF6 in the drum. The |
| leak would have to occur over a long period, in order to create a large mass |
| of U02F2 and then sufficiently moderate the material. |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.) |
| |
| "Double contingency is maintained by implementation of two controls on |
| moderation. |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL(INCLUDE PROCESS |
| LIMIT AND % WORST CASE CRITICAL MASS); |
| |
| "The material in the Surge Drum is in a gaseous state. System NCS limit is |
| 1.7 wt.% U235. |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES |
| |
| "The first leg of double contingency is based on maintaining the integrity |
| of the surge drum system against wet air in leakage. This integrity is |
| assured by a SRI for the unlikely breach of the surge drum system. |
| Structural integrity of the drum is intact, therefore this SRI is |
| maintained. |
| |
| "The second leg of double contingency is based on the performance of shiftly |
| pressure checks using an AQ-NCS instrument as an indication of wet air |
| in-leakage. The required checks could not be performed due to a failed |
| instrument, resulting in a loss of this control. Instead of installing a |
| sample buggy to measure pressure, the drum pressure was reduced in order to |
| read the pressure on the 0-2 pressure chart recorder. Since there are two |
| controls on one parameter, double contingency was not maintained. |
| |
| "Even though moderation control was maintained, double contingency is based |
| on two controls on moderation. Therefore, double contingency was not |
| maintained. |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS |
| IMPLEMENTED: |
| |
| None." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39589 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 02/16/2003|
| UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 03:10[EST]|
| RXTYPE: [1] CE |EVENT DATE: 02/16/2003|
+------------------------------------------------+EVENT TIME: 02:53[EST]|
| NRC NOTIFIED BY: STAN ROGERS |LAST UPDATE DATE: 02/16/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNUSUAL EVENT |Patrick Hiland IRO |
|10 CFR SECTION: |SONIA BURGESS R3 |
|AAEC 50.72(a) (1) (i) EMERGENCY DECLARED |JOHN ZWOLINSKI NRR |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| NOUE DECLARED DUE TO REDUCED PLANT SERVICE WATER FLOW |
| |
| Licensee reported that service water pump intake bay level decreased |
| requiring the shutdown of one dilution water pump to increase bay level to |
| normal. Flow was reduced on the operating dilution water pump by throttling |
| the discharge flow to maintain bay level at the normal operating level. The |
| cause of the reduced service water bay level is being investigated. The |
| licensee has notified the State of Michigan and VanBuren county. The |
| licensee will contact the NRC Resident Inspector. |
| |
| Notified FEMA of this event |
| |
| * * * UPDATE AT 0418 EST ON 2/16/03 BY GERRY WAIG * * * |
| |
| NRC entered monitoring phase of normal mode for this event at 0418 EST on |
| 2/16/03 after decision maker brief (Jim Dyer, Geoffrey Grant, Tony Vegel, |
| Pat Hiland, and John Zwolinski). |
| |
| * * * UPDATE AT 0825 EST ON 2/16/03 BY GERRY WAIG * * * |
| |
| NRC exited monitoring phase of normal mode for this event at 0825 EST on |
| 2/16/03 after briefing (J. Dyer/ R3 IRC members, S. Collins, J. Zwolinski, |
| R. Zimmerman, D. Wessman, W. Kane, & P. Hiland). |
| |
| * * * UPDATE AT 1600 EST ON 2/16/03 BY HOWIE CROUCH * * * |
| |
| Divers are at Palisades and preparing to inspect (most likely tomorrow). |
| The plant is stable and the bay level is stable. The plant continues in the |
| Unusual Event. Exit criteria will be root cause discovery. It was noted |
| that South Haven municipal water (near Palisades) was experiencing like |
| symptoms. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39590 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 02/17/2003|
| UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 13:34[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 02/17/2003|
+------------------------------------------------+EVENT TIME: 10:58[CST]|
| NRC NOTIFIED BY: KEVIN JONES |LAST UPDATE DATE: 02/17/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BRUCE BURGESS R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION OF SEPTIC SYSTEM OVERFLOW |
| |
| "On 2/17/03 at 1058, Xcel Energy Environmental Services completed |
| notification to the Minnesota Pollution Control Agency (MPCA) concerning an |
| approximately 300 gallon septic system overflow event. The distribution |
| system appears to be frozen due to cold weather and lack of snow cover, |
| causing the pump discharge to flow out to grade. Spill has been contained |
| and cleanup completed." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39591 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 02/17/2003|
| UNIT: [] [2] [] STATE: CA |NOTIFICATION TIME: 13:57[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/17/2003|
+------------------------------------------------+EVENT TIME: 08:30[PST]|
| NRC NOTIFIED BY: JEFF KNISLEY |LAST UPDATE DATE: 02/17/2003|
| HQ OPS OFFICER: ARLON COSTA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHARLES MARSCHALL R4 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION FOR ISOLATION CAPABILITY OF MANUAL VALVES IN THE |
| COMPONENT COOLING WATER SYSTEM |
| |
| "During the eleventh refueling outage on Unit 2 (2R11), component cooling |
| water (CCW) system manual valve CCW-2-18 was found to have a damaged liner. |
| The subject valve is used to separate the two vital normally cross-tied CCW |
| trains in case of a CCW leak either as an independent event or as a passive |
| failure following a loss of coolant accident. Valve CCW-2-18 would not have |
| performed its licensing/design function of providing CCW train isolation. |
| |
| "The licensing/design bases for this CCW System, as discussed in table 9.2-7 |
| of the FSAR and in SSER 16, is for a maximum 200 gpm leak to occur. Leakage |
| would be detected by falling level in the CCW surge tank. Because of the |
| remaining 4000 gallons in the CCW surge tank after receipt of the low-level |
| alarm, there would be at least 20 minutes for the operator to isolate the |
| leak before the surge tank is empty. The period is extended if the |
| automatically operated, Design Class II, normal makeup path functions as |
| designed and adds makeup water to the system. PG&E's abnormal operating |
| procedure, OP AP-11, has provision for aligning a 250 gpm Class I supply of |
| water to the CCW surge tank. |
| |
| "The design/licensing basis of a 200 gpm leak being isolated in 20 minutes |
| assumes that manual valves used during the isolation operation hold and |
| terminate the leak. There is no evidence that PG&E nor the NRC have |
| considered that a leak would not be isolated upon completion of actions to |
| separate the trains. The identified condition, though not believed to |
| represent a safety concern, is different than that discussed in SSER 16. |
| Therefore, the condition is considered to be outside the design basis for |
| the plant." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39592 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 02/17/2003|
| UNIT: [1] [] [] STATE: FL |NOTIFICATION TIME: 15:29[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 02/17/2003|
+------------------------------------------------+EVENT TIME: 14:13[EST]|
| NRC NOTIFIED BY: JOE HESSLING |LAST UPDATE DATE: 02/17/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK LESSER R2 |
|10 CFR SECTION: | |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 8-HOUR NON-EMERGENCY NOTIFICATION DUE AUTOMATIC START AND LOAD OF THE 1B |
| EMERGENCY DIESEL GENERATOR |
| |
| The following information was obtained from the licensee via facsimile: |
| |
| "While performing maintenance activities to replace a failed undervoltage |
| relay on 1B3 4160 VAC bus, the undervoltage protection triggered a load shed |
| on the 1B3 4160 VAC bus causing a loss of power to the bus and automatic |
| start and load of the 1B Emergency Diesel Generator. Although the potential |
| for this event was previously briefed for the relay replacement, this event |
| is being reported under 10CFR50.72(b)(3)(iv)(A)." |
| |
| The load shed caused a loss of the 1B motor-generator (MG) set but both MG |
| sets are 100% capacity sets. There were no adverse consequences due to the |
| trip of the 1B MG set. |
| |
| The licensee has informed the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 39593 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CARBOLINE COMPANY |NOTIFICATION DATE: 02/17/2003|
|LICENSEE: CARBOLINE COMPANY |NOTIFICATION TIME: 16:44[EST]|
| CITY: BRENTWOOD REGION: 3 |EVENT DATE: 02/17/2003|
| COUNTY: STATE: MO |EVENT TIME: [CST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 02/17/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN ZWOLINSKI NRR |
| |CHARLES MARSCHALL R4 |
+------------------------------------------------+SONIA BURGESS R3 |
| NRC NOTIFIED BY: MARIKAY SPECHERT |MARK LESSER R2 |
| HQ OPS OFFICER: HOWIE CROUCH |GLENN MEYER R1 |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 10 CFR PART 21 NOTIFICATION - CARBOLINE COMPANY |
| |
| The following information was obtained from the vendor via facsimile: |
| |
| "This letter serves to notify the Commission of a potential safety related |
| noncompliance deviation in a basic component as defined in 10CFR Part 21. |
| The noncompliance involves hard settling of Carboguard 890 Part B; the |
| affected batches are 2A9266L, 2A9275L, and 2H9352L |
| |
| "The hard settling of Carboguard 890 Part B would result in a mixed product |
| that would have lower pigment volume concentration (PVC) than standard |
| material that has been uniformly dispersed. Potential deficiencies would be |
| a lack of film build during application as a result of a lower initial |
| viscosity and the fact that some particles from the hard settling may have |
| been dispersed into the mixed product. These particles could result in the |
| clogging of spray gun tips or having particles embedded into the applied |
| coating, which are aesthetically unpleasing. Overall the lack of pigment in |
| the coating film affects the application and aesthetic properties of the |
| coating and not the performance properties. The primary criteria for the |
| epoxy coating's performance are that the stoichiometry of epoxy resin to |
| amine curing agent are not changed by more than 10%. Based upon a prior |
| non-nuclear occurrence we know that the hard settling does not alter the |
| stoichiometry of the coating and the cure of the product will be within the |
| parameters designed by the formulating chemist. Based upon prior testing of |
| numerous coatings for use in nuclear power plants we have not seen any |
| detrimental performance when lower PVC coatings were evaluated. Resin rich |
| coatings are typically gloss coatings and they aid in radiation |
| decontamination and chemical resistance. As such, Carboline does not feel |
| that the performance of the coating will be adversely affected. |
| |
| "A database has been created documenting all shipments of the affected |
| batches made within the 2002 calendar year to present; approximately 30 |
| utilities/customers are affected. All customers who our records indicate |
| have been shipped batches 2A9266L, 2A9275L, and 2H9352L shall be notified |
| promptly. We are requesting that customers review their stock of Carboguard |
| 890 Part B and return the affected batches for replacement. |
| |
| "In summary, Carboline has taken appropriate corrective action, notified the |
| NRC, and shall notify all customers promptly." |
| |
| The affected parties are as follows: |
| Consumers Energy - Palisades Generating Plant |
| Energy Steel & Supply - 2715 Padan Street, Auburn Hills, MI |
| Florida Power & Light - 9760 SW 344th St., Florida City, FL |
| Hutchinson & Gunter - 715 Grpve Street, Greensburg, PA |
| Imaging & Sensing Technology - IST Conax Nuclear, Inc., Buffalo, NY |
| Newbury Sandblasting - PO Box 378, Newbury, OH |
| Nullifire Ltd. - Torrington Avenue, Coventry, UK |
| Point Beach Nuclear - 6610 Nuclear Road, Two Rivers, WI |
| Prairie Island - Welch, MN |
| Ameren/UE-CIPS - Callaway Plant |
| Duke Energy Corp - Nuclear Assessment Division, SC |
| Ellis & Watts - 4325 Slick Lane, Bativa, OH |
| FirstEnergy, Davis-Besse Oak Harbor, OH |
| Howden Buffalo - New Philadelphia, OH |
| Omaha Public Power - Fort Calhoun Nuclear Station |
| Palmer Industrial Coatings - Williamsport, PA |
| Rotork Controls - Rochester, NY |
| TXU Electric - Glen Rose, TX |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39595 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 02/18/2003|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 12:40[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 02/18/2003|
+------------------------------------------------+EVENT TIME: 12:00[EST]|
| NRC NOTIFIED BY: CHARLES PIKE |LAST UPDATE DATE: 02/18/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CHARLES R. OGLE R2 |
|10 CFR SECTION: |ROBERTA WARREN IAT |
|DDDD 73.71(b)(1) SAFEGUARDS REPORTS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 1- HOUR SAFEGUARDS REPORT |
| |
| Unescorted access granted to contract employee inappropriately. Immediate |
| compensatory measures taken upon discovery. Contact Headquarters Operations |
| Officer for details. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021