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Event Notification Report for December 14, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/13/1999 - 12/14/1999

                              ** EVENT NUMBERS **

36350  36495  36499  36503  36504  36505  36506  

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36350       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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:  12/13/1999|
|  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                                   
+------------------------------------------------------------------------------+
| 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 Hodges) have been notified.             |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36495       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WASHINGTON NUCLEAR (WNP-2REGION:  4  |NOTIFICATION DATE: 12/08/1999|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 20:01[EST]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        12/08/1999|
+------------------------------------------------+EVENT TIME:        13:30[PST]|
| NRC NOTIFIED BY:  BRIAN ADAMI                  |LAST UPDATE DATE:  12/13/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOSEPH TAPIA         R4      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD  |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INOPERABILITY OF HIGH PRESSURE CORE SPRAY DUE TO A POTENTIALLY               |
| NON-CONSERVATIVE CALCULATED DUTY LOAD CYCLE LOAD PROFILE FOR THE BATTERY     |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "This is a 4-hour Non-Emergency report in accordance with 10 CFR 50.72       |
| (b)(2)(iii)(A) due to the High Pressure Core Spray (HPCS) system being       |
| declared inoperable at 1330 hours PST on December 8, 1999.  The plant        |
| remains in Mode 1 as allowed by plant technical specifications with the      |
| Reactor Core Isolation Cooling (RCIC) system operable."                      |
|                                                                              |
| "HPCS was declared inoperable due to the HPCS battery being declared         |
| technically inoperable.  The battery was conservatively declared inoperable  |
| because the calculated duty cycle load profile that is used for the          |
| acceptance criteria in the surveillance for SR 3.8.4.7 appeared to be        |
| non-conservative.  It is likely that a lower than actual breaker spring      |
| charging motor inrush current was used in the calculation.  Charging motor   |
| current is being confirmed by the vendor[, General Electric]."               |
|                                                                              |
| The licensee stated that the unit is in a 14-day limiting condition for      |
| operation as a result of this issue.                                         |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * RETRACTED AT 1709 EST ON 12/13/99 BY J. W. GASTON TO FANGIE JONES * *  |
| *                                                                            |
|                                                                              |
| "This notification is made to retract event report # 36495 made on 12/8/99   |
|                                                                              |
| "HPCS had been declared inoperable due to the HPCS battery being declared    |
| inoperable. The battery was declared inoperable because the calculated load  |
| profile was found to be non-conservative. This invalidated the last battery  |
| surveillance service test performed for the 24 month Surveillance            |
| Requirement 3.8.4.7 because the service test discharge profile was taken     |
| from the errant calculation.  Upon recalculating the duty cycle profile and  |
| reviewing other previously performed service test results it has been        |
| determined that a discharge profile used for a service test that was         |
| performed on 8/16/98 bounds the recalculated duty cycle for the HPCS         |
| battery. Therefore, the Surveillance Requirement 3.8.4.7 is met and no       |
| reportable condition exists."                                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R4DO (Phil Harrell)   |
| was notified.                                                                |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36499       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 12/10/1999|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 17:19[EST]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        12/10/1999|
+------------------------------------------------+EVENT TIME:        14:00[EST]|
| NRC NOTIFIED BY:  BRETT BOISMENU               |LAST UPDATE DATE:  12/13/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLIFFORD ANDERSON    R1      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - FITNESS FOR DUTY REPORT -                                                  |
|                                                                              |
| A CONTRACTOR SUPERVISOR FAILED HIS INITIAL PRE-PLANT ACCESS AUTHORIZATION    |
| DRUG TEST.  THE INDIVIDUAL WAS NOT GRANTED PLANT ACCESS AUTHORIZATION AND HE |
| WAS REFERRED TO HIS EMPLOYER.                                                |
|                                                                              |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR.                     |
|                                                                              |
| * * * RETRACTED AT 1234 EST ON 12/13/99 BY BRIAN WEAVER TO ROBERT STRANSKY * |
| * *                                                                          |
|                                                                              |
| "Following a review from our Licensing Department, the individual in         |
| question had not been granted access and was outside the scope of 10CFR26."  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R1DO (Clifford        |
| Anderson) has been notified.                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36503       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 12/13/1999|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 11:57[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        12/13/1999|
+------------------------------------------------+EVENT TIME:        11:09[EST]|
| NRC NOTIFIED BY:  KEVIN ABELL                  |LAST UPDATE DATE:  12/13/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| FIRE WRAP DISCOVERED  IMPROPERLY INSTALLED AT INTERFACE WITH FIRE SEAL       |
|                                                                              |
| "On December 13, 1999 while operating at 100% power, Harris Nuclear Plant    |
| (HNP) discovered fire wrap improperly installed on an individual electrical  |
| conduit at the interface between the fire wrap and fire seal. This condition |
| was identified as part of field walkdowns of cable fire wrap installations   |
| associated with a recent NRC Fire Protection inspection. Initial             |
| investigation has determined that in the event of a fire under certain       |
| circumstances HNP could not achieve and maintain a safe shutdown due to a    |
| loss of instrumentation used to verify natural circulation. HNP has          |
| established a 1 hour roving fire watch in the area as a compensatory measure |
| until this issue is resolved since fire detection and suppression are        |
| available in the area. This condition is being reported as a condition       |
| outside of the design bases (10CFR50.72.(b)(I)(ii)(B))."                     |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   36504       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  BLUE RIDGE NUCLEAR PHARMACY          |NOTIFICATION DATE: 12/13/1999|
|LICENSEE:  BLUE RIDGE NUCLEAR PHARMACY          |NOTIFICATION TIME: 16:40[EST]|
|    CITY:  ROANOKE                  REGION:  2  |EVENT DATE:        12/13/1999|
|  COUNTY:                            STATE:  VA |EVENT TIME:        15:45[EST]|
|LICENSE#:  45-25339-01           AGREEMENT:  N  |LAST UPDATE DATE:  12/13/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |AL BELISLE           R2      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ROBERT BEIGHTOL              |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PACKAGE LOST CONTAINING TWO THERAPEUTIC DOSE CAPSULES OF IODINE-131          |
|                                                                              |
| Lewis Gale Hospital of Salem, VA contacted the licensee that an expected     |
| delivery of two therapeutic doses of Iodine-131 did not arrive 12/13/99.     |
| The licensee checked the cabinet where the package was placed on the         |
| afternoon of 12/10/99 and did not find it.  They checked with their delivery |
| department and the package was not taken out by them.  The licensee further  |
| checked with the courier service that picked up expended generators from the |
| same cabinet, they did not have it either.  At that time when the other      |
| possible courier couldn't be contacted, the NRC was informed of the missing  |
| package.   The licensee will continue to try contacting the other courier    |
| service about the package.                                                   |
|                                                                              |
| * * * UPDATE AT 1700 EST ON 12/13/99 BY ROBERT BEIGHTOL TO FANGIE JONES * *  |
| *                                                                            |
|                                                                              |
| The other courier service was contacted and the package was located.  It is  |
| presently in locked storage and will be returned tomorrow, 12/14/99 to the   |
| licensee.  The R2DO (Al Belisle) and NMSS (Don Cool) were informed.          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36505       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ARIZONA RADIATION REGULATORY AGENCY  |NOTIFICATION DATE: 12/13/1999|
|LICENSEE:  CONSTRUCTION INSPECTION & TESTING CO.|NOTIFICATION TIME: 18:05[EST]|
|    CITY:  PHOENIX                  REGION:  4  |EVENT DATE:        12/13/1999|
|  COUNTY:                            STATE:  AZ |EVENT TIME:        15:00[MST]|
|LICENSE#:  AZ7-98                AGREEMENT:  Y  |LAST UPDATE DATE:  12/13/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |PHIL HARRELL         R4      |
|                                                |JOHN SURMEIER        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  AUBREY GODWIN                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| RECOVERY OF TROXLER MOISTURE-DENSITY GAUGE STOLEN IN 1995                    |
|                                                                              |
| The following is a portion of a facsimile from Arizona Radiation Regulatory  |
| Agency:                                                                      |
|                                                                              |
| "This First Notice constitutes early notice of events of possible safety or  |
| public interest significance. The information is as initially received       |
| without verification or evaluation, and is basically all that is known by    |
| the Agency Staff at this time.                                               |
|                                                                              |
| First Notice #: 95-4                                                         |
|                                                                              |
| "On October 11, 1995, the Licensee notified the Agency that a Troxler Model  |
| 3440 moisture-density gauge was stolen from a garage in a pickup truck. The  |
| gauge was chained to the truck in the shipping container and is serial       |
| number 21861. This was also reported to the Phoenix Police Department and    |
| their report is number 95-008240. On December 11, 1999, the Phoenix Fire     |
| Department reported the location of the gauge to the Agency after they been  |
| notified by the Phoenix Police Department. The Licensee has been informed of |
| the location of the gauge at the  Agency. A leak test indicates the sources  |
| are not leaking. The gauge was located by an individual who remember that a  |
| reward was offered, in some cases, for the return of a gauge.                |
|                                                                              |
| "The gauge and case were without any locking devices. All label and tags     |
| identifying the owner had disappeared. All indications are that the gauge    |
| had been in the desert for an extended period of time.                       |
|                                                                              |
| "The FBI, U.S. Nuclear Regulatory Commission, Mexico, and the States of      |
| California, Colorado, Nevada, Utah, and New Mexico are being notified of     |
| this incident."                                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36506       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 12/14/1999|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 00:27[EST]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        12/13/1999|
+------------------------------------------------+EVENT TIME:        20:45[CST]|
| NRC NOTIFIED BY:  DAVE BOWMAN                  |LAST UPDATE DATE:  12/14/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SHEAR           R3      |
|10 CFR SECTION:                                 |                             |
|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          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFETY SYSTEM FAILURE:  THE BREAKER FOR THE "B" TRAIN REFRIGERATION CONTROL  |
| UNIT (RCU) TRIPPED.                                                          |
|                                                                              |
| The licensee started the "B" control room HVAC to support routine            |
| maintenance on "A" train.  "B" train would not operate properly on           |
| non-safety related cooling (station service water); safety related cooling   |
| (RHR service water ) was started to provide cooling to the "B" train, which  |
| operated properly on safety related cooling.  After the control room had     |
| cooled down, "B" train was shut down and then restarted with non-safety      |
| related cooling, after which it operated properly.   During subsequent swap  |
| to the "A" train, the breaker for "B" train RCU tripped.  This is a safety   |
| system functional failure.  The licensee entered Technical Specification     |
| 3.8.D.1.b for RCU inoperable, which is a 30 day Limiting Condition of        |
| Operation.  Troubleshooting of the problem is in progress.                   |
| This is part of the Control Room Emergency Ventilation System.               |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+