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
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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: 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
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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 Hodges) have been notified. |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 36495 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| 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. |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|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
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| - 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. |
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|Power Reactor |Event Number: 36503 |
+------------------------------------------------------------------------------+
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| 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
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| 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 |
+------------------------------------------------------------------------------+
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| 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
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| 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. |
+------------------------------------------------------------------------------+
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|General Information or Other |Event Number: 36505 |
+------------------------------------------------------------------------------+
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| 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
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| 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. |
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