Event Notification Report for March 7, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/06/2000 - 03/07/2000
** EVENT NUMBERS **
36350 36758 36759 36760 36761
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|General Information or Other |Event Number: 36350 |
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| REP ORG: TECHNOLOGY for ENERGY CORP. |NOTIFICATION DATE: 10/26/1999|
|LICENSEE: TECHNOLOGY for ENREGY CORP. |NOTIFICATION TIME: 13:48[EDT]|
| CITY: KNOXVILLE REGION: 2 |EVENT DATE: 10/26/1999|
| COUNTY: STATE: TN |EVENT TIME: 13:48[EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 03/06/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MARK LESSER R2 |
| |VERN HODGE NRR |
+------------------------------------------------+DAVID LEW R1 |
| NRC NOTIFIED BY: JEFF LOLLAR |MIKE JORDAN R3 |
| HQ OPS OFFICER: JOHN MacKINNON |DAVID LOVELESS R4 |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| RTV SEALANT USED IN THE TEC VALVE FLOW MONITORING SYSTEM CANNOT BE |
| DEMONSTRATED TO MEET THE CONTAINMENT QUALIFICATION CONDITIONS. |
| |
| 10 CFR Part 21 Interim Report submitted by Technology for Energy Corporation |
| (TEC), located in Knoxville, TN. |
| |
| TEC is reporting a potential defect in Valve Flow Monitoring Systems |
| provided by TEC to the nuclear power industry. Further evaluation is |
| required to determine if the subject condition constitutes a defect as |
| defined in 10CFR21.3. |
| |
| The RTV-738 sealant used in the TEC Valve Flow Monitoring System cannot be |
| demonstrated to meet the containment qualification conditions. |
| |
| During discussions with customers concerning the application of RTV-738 |
| sealant at the accelerometer connection to hardline cable, it was discovered |
| that the recommended installation procedure was not specified during the |
| qualification test (1980). One witness to the qualification test confirm |
| that the RTV-738 was present but further stated it had been removed and |
| replaced between qualification stages (aging, irradiation, seismic, and |
| LOCA). Records cannot confirm if this was the test condition, but a set of |
| cable resistance measurements suggest the RTV-738 was removed in order to |
| perform the resistance testing. This uncertainty impacts the qualified life |
| of the Valve Flow Monitoring System since the accelerometer to hardline |
| cable could be exposed to LOCA conditions and the RTV-738 is applied to seal |
| the junction between these components. Internal Corrective Action Report # |
| 0026 has been initiated to track this condition. |
| |
| |
| After confirming that documentation was not available to conclusively |
| demonstrate the qualified test conditions, a new qualification test plan was |
| generated and has started. This testing is designed to demonstrate if the |
| accelerometer to hardline cable junction can be qualified not only using |
| RTV-738 , but also without RTV-738 and with Raychem heat shrink. Thermal |
| aging is complete without failure and irradiation is now underway. The full |
| test is expected to be completed by December 10, 1999 with the final LOCA |
| testing phase scheduled to start on November 8, 1999. |
| |
| There have been no reported failures of the accelerometer to hardline cable |
| junction except due to physical damage during outages. Therefore, no action |
| is recommended at this time pending verification of the qualified assembly |
| both with and without the RTV-738 sealant. |
| |
| * * * UPDATE AT 1508 EST ON 12/13/99 BY RONALD BRENNER TO FANGIE JONES * * |
| * |
| |
| "Technology for Energy Corporation has been advised that accident simulation |
| testing of accelerometer/hardline cable junctions by Wyle Laboratories will |
| not be completed until December 23, 1999. The NRC will be notified of any |
| further change in the status of this testing. |
| |
| The R1DO (Clifford Anderson), R2DO (Al Belisle), R3DO (Gary Shear), R4DO |
| (Phil Harrell) and NRR Part 21 (Vern Hodge) have been notified. |
| |
| ******* UPDATE AT 1017 ON 03/06/00 VIA FACSIMILE FROM RONALD BRENNER TO |
| LEIGH TROCINE ******* |
| |
| The following text is a portion of a facsimile received from Technology for |
| Energy Corporation: |
| |
| "Subject: NRC Event Report Number 36350" |
| |
| "In an October 26, 1999, Interim Report, Technology for Energy Corporation |
| (TEC) notified the NRC that TEC was evaluating a potential defect involving |
| a hardline cable/accelerometer junction (the Junction) in the TEC Model 1414 |
| Valve Flow Monitoring (VFM) System. The purpose of TEC's evaluation was to |
| determine if the use of Dow Coming RTV738 Sealant (RTV738) at the Junction |
| constituted a defect as defined in 10CFR21.3." |
| |
| "TEC has completed its final determination of reportability. A full range |
| of thermal aging, radiation aging, seismic testing, and LOCA testing |
| demonstrated that the RTV738 protected the Junction in a harsh environment. |
| Therefore, TEC concludes that the use of the RTV738 in its Model 1414 VFM |
| System has been demonstrated to meet the qualification conditions as |
| delineated in TEC Report Number 517-TR-03, Revision 2, dated December 1, |
| 1981." |
| |
| "Based on this evaluation, TEC concludes the following: |
| |
| 1. The Junction configuration does not create a substantial safety hazard, |
| and no industry corrective action |
| is required. |
| 2. There is no evidence of a defect as defined in 10CFR21.3. |
| 3. TEC's evaluation pertaining to subject event is hereby closed." |
| |
| The NRC operations officer notified the R1DO (Cranston), R2DO (Wert), R3DO |
| (Lanksbury), R4DO (Loveless), and NRR (Hodge). |
| |
| (Contact the NRC operations officer for a contact address and telephone |
| number.) |
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|Power Reactor |Event Number: 36758 |
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| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 03/06/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 02:39[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 03/05/2000|
+------------------------------------------------+EVENT TIME: 22:00[CST]|
| NRC NOTIFIED BY: STEVEN JOBE |LAST UPDATE DATE: 03/06/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| FAILURE TO MEET DRYWELL-TO-SUPPRESSION CHAMBER LEAKAGE TEST ACCEPTANCE |
| CRITERIA |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "The acceptance criteria specified for the DRYWELL-TO-SUPPRESSION CHAMBER |
| LEAKAGE TEST was not met. The as-found value of 0.51 [inches] H2O/Min |
| exceeded the operability value of <= 0.2 [inches] H2O/Min. Based on this, |
| the operability of the drywell-to-suppression chamber vent pipes, vent |
| header downcomers, and vacuum breakers cannot be assumed. Primary |
| containment was declared inoperable based on a failure to meet the |
| requirements of [surveillance requirement (SR)] 3.6.1.1.2, Verify drywell to |
| suppression chamber bypass leakage is equivalent to a hole < 1.0 inch in |
| diameter." |
| |
| "[The unit] entered [limiting condition for operation (LCO)] 3.6.1.1, |
| Condition A, requiring the restoration of primary containment to an operable |
| status within 1 hour. If this required action is not met, Condition B.1 |
| requires having the reactor in Mode 3 within 12 hours and B.2 requires |
| having the reactor in Mode 4 within 36 hours." |
| |
| "Currently[, the unit is] in Mode 3 for commencing [a] planned refueling |
| outage." |
| |
| "Engineering evaluation of test results is continuing, and the resident |
| inspectors will be kept apprised." |
| |
| The licensee notified the NRC resident inspectors. |
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|General Information or Other |Event Number: 36759 |
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| REP ORG: TENNESSEE DIV OF RAD HEALTH |NOTIFICATION DATE: 03/06/2000|
|LICENSEE: CLINICAL PHARMACY SERVICES |NOTIFICATION TIME: 09:08[EST]|
| CITY: GRAY REGION: 2 |EVENT DATE: 03/01/2000|
| COUNTY: STATE: TN |EVENT TIME: [EST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 03/06/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LEN WERT R2 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+JOSEPH GIITTER IRO |
| NRC NOTIFIED BY: DEBRA SHULTS (DRH) | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
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EVENT TEXT
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| AGREEMENT STATE REPORT INVOLVING AN IODINE-131 SPILL AT CLINICAL PHARMACY |
| SERVICES LOCATED IN GRAY, TENNESSEE |
| |
| The following text is a portion of a facsimile received from the State of |
| Tennessee, Department of Environmental Conservation, Division of |
| Radiological Health (DRH): |
| |
| "Event Report ID No.: TN-00-038" |
| |
| "Event date and time: March 1, 2000" |
| |
| "Event location: Gray, Tennessee" |
| |
| "Event type: Contamination event" |
| |
| "Event description: DRH was notified on 03/03/00 by a representative from |
| Clinical Pharmacy Services of an iodine-131 spill in the pharmacy on |
| 03/01/00. When moving a pig with syringe from one hood to another for dose |
| calibration, the end of the syringe plunger caught on part of the hood and |
| was pulled out. Most of the 150 millicuries of I-131 was lost and |
| contaminated the area. The area read 150 mR/hr. This was shielded to 50 |
| mR/hr with lead. The area was cleaned and covered to an extent, but this |
| was discontinued when clothing and badges became contaminated. They have |
| discontinued work in the room and I-131 preparation. They will distribute |
| unit commercial doses for now. They have a hood in another room for their |
| other work. The unrestricted air concentration was 10,000 times the limit. |
| The occupational dose was 72% of the limit. Bioassays were performed. A |
| written report will be submitted." |
| |
| (Call the NRC operations officer for a State of Tennessee, Department of |
| Environmental Conservation, Division of Radiological Health, contact name |
| and telephone number.) |
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|Power Reactor |Event Number: 36760 |
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| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 03/06/2000|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 13:38[EST]|
| RXTYPE: [3] CE |EVENT DATE: 03/06/2000|
+------------------------------------------------+EVENT TIME: 11:45[CST]|
| NRC NOTIFIED BY: JON GLUECK |LAST UPDATE DATE: 03/06/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID LOVELESS R4 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |95 Power Operation |
| | |
| | |
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EVENT TEXT
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| - TECH SPEC REQUIRED PLANT SHUTDOWN DUE TO SMALL UNISOLABLE LEAK IN THE CVC |
| SYSTEM - |
| |
| At 1145 CST on 03/06/00, the licensee entered Tech Spec 3.0.3 due to |
| visually observing a small crack (approximately 1/4 inch long) located at a |
| welded joint in the suction line of the 'A' Charging and Volume Control |
| (CVC) pump, leaking approximately 1 drop every 2 minutes. This rendered the |
| entire CVC System inoperable. The leaking weld is unisolable from the |
| entire charging header. |
| |
| Tech Spec 3.1.2.4 requires at least two charging pumps to be operable in |
| Modes 1, 2, 3, and 4. With only one charging pump operable, restoration of |
| at least two charging pumps to operable status within 72 hours is required. |
| Currently, the leakage is not preventing the system from performing its |
| design function. The most closely affected charging pump has been secured |
| to limit the line vibration, which is the apparent cause of the leak. |
| |
| At 1222 CST on 03/06/00, the licensee commenced a plant shutdown from 100% |
| power. Tech Spec 3.0.3 requires the plant to be in Hot Standby Mode within |
| 6 hours. The licensee plans to cool the plant down to repair the leaking |
| weld. |
| |
| The licensee notified the NRC Resident Inspector. |
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|General Information or Other |Event Number: 36761 |
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| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 03/06/2000|
|LICENSEE: GCT INSPECTION , INC |NOTIFICATION TIME: 16:05[EST]|
| CITY: SOUTH HOUSTON REGION: 4 |EVENT DATE: 02/29/2000|
| COUNTY: STATE: TX |EVENT TIME: 12:00[CST]|
|LICENSE#: TX-2378 AGREEMENT: Y |LAST UPDATE DATE: 03/06/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DAVID LOVELESS R4 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: HELEN WATKINS | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
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EVENT TEXT
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| AGREEMENT STATE REPORT - RADIOGRAPHER RECEIVED ANNUAL EXPOSURE OF 5.205 Rem |
| IN 1999 - |
| |
| On 02/29/00, Texas Department of Health Bureau of Radiation Control received |
| notification from GCT Inspection, Inc, South Houston, TX, that a |
| radiographer had received an annual exposure of 5.205 Rem during 1999. 3.34 |
| Rem had been received in the 09/15/99 - 10/14/99 monitoring time period. TX |
| Department of Health Bureau of Radiation Control personnel are requesting |
| additional information and investigating this incident. |
| |
| TX Incident #7574. |
| |
| (Call the NRC operations officer for a state contact telephone number.) |
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Page Last Reviewed/Updated Thursday, March 25, 2021