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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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