Event Notification Report for October 27, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/26/1999 - 10/27/1999
** EVENT NUMBERS **
36266 36267 36296 36314 36347 36348 36349 36350 36351 36352 36353
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36266 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 10/06/1999|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 18:15[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/06/1999|
+------------------------------------------------+EVENT TIME: 17:45[EDT]|
| NRC NOTIFIED BY: DAUGHERTY |LAST UPDATE DATE: 10/26/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 |
|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 |
|2 N Y 90 Power Operation |90 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ERROR FOUND IN LARGE BREAK LOCA ANALYSIS |
| |
| "Westinghouse Letter DLC-99-768 reported errors found in the Large Break |
| LOCA analysis for both Beaver Valley units. These errors resulted in |
| calculated maximum Peak Clad Temperatures >2200�F with out taking credit for |
| any other available margins. Per 10CFR50.46.a.3.(ii), any change or error |
| correction that results in a calculated ECCS performance (where Peak Clad |
| Temperature is not maintained <2200�F) Is reportable per 10CFR50.72 |
| |
| "It should be noted that Westinghouse Letter DLC-99-768 proposed a more |
| conservative restriction on FQ limits for both units, and a more |
| conservative limit on Steam Generator tube plugging at unit 2 that would |
| overcome the effects of the reported errors. These limits are presently |
| being met and have been met for the time periods of the present cycles at |
| both units, so that the proposed analysis appears to be valid. Engineering |
| evaluation is pending for final approval of these proposals." |
| |
| The licensee intends to notify the NRC Resident Inspector. |
| |
| * * * Retraction on 10/26/99 at 1430 ET by C. Hynes taken by MacKinnon at |
| 1458 ET * * * |
| |
| Available design margins in FQ and steam generator tube plugging at Unit 2 |
| were sufficient to offset the increase in PCT due to the identified errors |
| and maintain compliance with the ECCS Performance Criteria of 10 CFR 50.46. |
| Utilizing these design margins has necessitated reduction of the FQ |
| surveillance limits in the Core Operating Limits Report. Administrative |
| controls were implemented on 10/08/99 to achieve this reduction in the FQ |
| surveillance limits. A review of completed flux maps has shown that the |
| reduced FQ limit has been met for the present operating cycle. Current |
| steam generator tube plugging levels were also confirmed to be less than the |
| reduced limit. Subsequent engineering review has confirmed that the |
| evaluations performed by Westinghouse show that all applicable safety |
| analysis acceptance criteria continue to be met. Recovery of available |
| margin results in a PCT that has in the past and presently remains < 2000 F. |
| As such, the basis for retraction of the 10CFR50.72 notification on 10/06/99 |
| is that this condition does not place either Unit outside its design basis. |
| However, this condition is applicable to the 30 day reporting criteria of 10 |
| CFR 50.46(a)(3)(ii). R1DO (David Lew) notified. |
| |
| The NRC Resident Inspector was notified of this retraction by the licensee.. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36267 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 10/06/1999|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 18:28[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/06/1999|
+------------------------------------------------+EVENT TIME: 16:40[EDT]|
| NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 10/26/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN KINNEMAN R1 |
|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 99 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH TRAINS OF LOW PRESSURE COOLANT INJECTION DECLARED INOPERABLE |
| |
| During periodic inspections, technicians discovered multiple loose battery |
| terminal connections on both UPS-1A and UPS-1B batteries. The licensee was |
| uncertain of the operability of the batteries and conservatively declared |
| both trains of low pressure coolant injection (LPCI) inoperable. This put |
| them in a 24-hour Technical Specification action statement (3.5.A.6) to |
| bring the plant to hot shutdown. Electrical maintenance is on site |
| tightening connections and inspecting all battery connections. The licensee |
| does not anticipate having to shutdown as electrical maintenance is working |
| now. An investigation into the event will follow up the event. |
| |
| The licensee notified the NRC Resident Inspector and the State of Vermont |
| Nuclear Engineer. |
| |
| |
| * * * Retraction on 10/26/99 at 1639 ET by Mark Magnuson taken by MacKinnon |
| * * * |
| |
| Vermont Yankee Design Electrical Engineering (EE) has since evaluated the |
| as-found condition of the battery terminals (interconnection plate fasteners |
| at less than the required torque). EE reviewed the as-found interconnection |
| resistance values. Those resistance values showed that the total resistance |
| created by the battery connections in the as-found configuration was |
| elevated by only 0.57%. The as-found resistance's also showed that the |
| highest resistance interconnection would, with running load placed upon the |
| battery, have induced a voltage drop of less than 0.002% of rated battery |
| voltage. Additionally, the potential heating of the highest resistance |
| interconnection plate assembly (under running load) was determined to be 0.6 |
| watt-hours. This is not sufficient energy to cause overheating of the |
| connection. |
| |
| EE's conclusion after a detailed assessment of the condition of the 2 UPS |
| batteries, is that they were operational at all times they were considered |
| operable. Therefore, they were fully capable of supporting operation of the |
| LPCI system. Therefore, this event is being retracted by the licensee. |
| |
| R1DO (David Lew) notified. The NRC Resident Inspector was notified by the |
| licensee of the retraction of the event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36296 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 10/15/1999|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 13:09[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 10/15/1999|
+------------------------------------------------+EVENT TIME: 10:00[EDT]|
| NRC NOTIFIED BY: BILL BANDHAUSER |LAST UPDATE DATE: 10/26/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| GREATER THAN 1% OF THE 'A' ONCE-THROUGH STEAM GENERATOR (OTSG) TUBES ARE |
| DEFECTIVE. |
| |
| Plant personnel determined that the inspection of the 'A' OTSG found 10 of |
| 528 tubes to have "indication of a defect" using the plus point probe |
| inspection of the lower tube sheet secondary face ding/dent population. |
| |
| Because there is no qualified sizing technique for circumferential |
| crack-like or volumetric indications in this region, it cannot be |
| demonstrated that the through-wall depth penetration of these indications is |
| less than 40% of the tube wall. Therefore, the tubes containing these |
| indications must be classified as "Defective." |
| |
| Since more than 1% of the sample size was determined to be defective, the |
| inspection result is classified as "C-3" as defined in paragraph |
| 5.6.2.10.2.f of the Crystal River Unit 3 Improved Technical Specifications |
| (ITS). |
| |
| Table 5.6.2-2 of Crystal River Unit 3 ITSs requires that this "C-3" result |
| be reported to the NRC per 10 CFR 50.72. |
| |
| This condition is considered to be a serious degradation of a principal |
| safety barrier (Reactor Coolant System) discovered while shutdown. |
| |
| Prior to the current Crystal River Unit 3 plant shutdown on 10/01/99, the |
| actual primary to secondary leakage through the 'A' OTSG was significantly |
| below the allowable limit of ITS 3.4.12.d (less that 150 gallons per day). |
| |
| The NRC Resident Inspector was notified of this event notification by the |
| licensee. |
| |
| * * * Update by Bandhauer on 10/26/99 at 1507ET taken by MacKinnon * * * |
| |
| |
| Upon further review, Florida Power Corporation (FPC) has determined that |
| none of the 10CFR50.72 reporting criteria applies to the results of this |
| inspection. Therefore, the basis for this notification is revised to |
| "require by ITS Table 5.6.2-2 and ITS 5.7.2.d." |
| |
| The OTSG Tube Surveillance Program is completed. Additional "C-3" |
| classifications are now being declared where more than 1% of sampled tubes |
| were determined to be defective. The inspected areas involve the "A" and |
| "B" OTSG upper roll transition/tube ends and the "B" OTSG sleeved tubes. |
| FPC has determined that none of the 10CFR50.72 reporting criteria applies to |
| the results of these inspections. Therefore, this supplemental notification |
| is being made because it is required by ITS Table 5.6.2-2 and ITS 5.7.2.d. |
| |
| Further information concerning the OTSG Tube Surveillance Program inspection |
| results will be provided in Mode 4 Report required by ITS 5.7.2.c. R2DO |
| (Mark Lesser) was notified. |
| |
| The NRC Resident Inspector was notified of this Update by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36314 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MISSISSIPPI DIV OF RAD HEALTH |NOTIFICATION DATE: 10/20/1999|
|LICENSEE: PRITCHARD ENGINEERING INC |NOTIFICATION TIME: 09:40[EDT]|
| CITY: STARKVILLE REGION: 2 |EVENT DATE: 10/19/1999|
| COUNTY: STATE: MS |EVENT TIME: 17:45[CDT]|
|LICENSE#: MS-865-01 AGREEMENT: Y |LAST UPDATE DATE: 10/26/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KERRY LANDIS R2 |
| |SCOTT MOORE EO NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: NELSON | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE MISSISSIPPI DIVISION OF RADIOLOGICAL HEALTH REPORTED A LOST MOISTURE |
| DENSITY GAUGE. |
| |
| PRITCHARD ENGINEERING INC. LOST A MOISTURE DENSITY GAUGE WHEN IT FELL OUT OF |
| THE BACK OF A TRUCK IN STARKVILLE, MS. THE GAUGE IS A CAMPBELL-PACIFIC |
| MODEL 131 SERIAL # MD80804480 CONTAINING 10 MILLICURIES OF CESIUM-137 AND 50 |
| MILLICURIES OF AMERICIUM-241/BERYLLIUM. THE DEVICE SHOULD BE LOCKED IN AN |
| ORANGE CONTAINER AND ALSO LOCKED AT THE GAUGE HANDLE. THE LOCAL SHERIFF AND |
| MISSISSIPPI HEALTH DEPARTMENT HAVE BEEN NOTIFIED. THEY ARE CURRENTLY |
| LOOKING FOR THE DEVICE. |
| |
| |
| *** UPDATE ON 10/26/99 @ 0945 BY NELSON TO GOULD *** |
| |
| THE GAUGE WAS FOUND ON 10/25/99 BY A SEARS SERVICEMAN ON A ROAD IN |
| MASHULAVILLE, MS. THE DEVICE WAS INTACT WITH ONLY MINOR DAMAGE TO THE CASE. |
| THE SEARS SERVICEMAN NOTIFIED THE MISSISSIPPI DEPARTMENT OF TRANSPORTATION |
| TO LOCATE AND RETURN THE DEVICE TO THE OWNER. THE OWNER TOOK POSSESSION OF |
| THE DEVICE LAST NIGHT. |
| |
| THE REG 2 RDO(LANDIS) AND NMSS EO(PICCONE) WERE NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36347 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 10/26/1999|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 03:06[EDT]|
| RXTYPE: [1] CE |EVENT DATE: 10/26/1999|
+------------------------------------------------+EVENT TIME: 01:32[CDT]|
| NRC NOTIFIED BY: LARRY LEES |LAST UPDATE DATE: 10/26/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: ALE |DAVID LOVELESS R4 |
|10 CFR SECTION: |BRUCE BOGER NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |JOSEPH GIITTER IRO |
| |CANUPP FEMA |
| |PERKINS DOE |
| |TURMAN EPA |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 1 REPORTED ENTERING AND EXITING CONDITIONS REQUIRING AN ALERT |
| DECLARATION |
| |
| "AT 0132CDT, WHEN ATTEMPTING TO TRANSFER STATION LIGHTING, VITAL BUSES 1A3 |
| AND 1A4 WERE DEENERGIZED. [BOTH] DIESEL GENERATORS [DG-1 AND DG-2] WERE IN |
| 'OFF-AUTO' FOR MODE 5 CONDITIONS. WHEN THE DIESEL GENERATORS WERE TAKEN TO |
| 'AUTO,' THE DIESEL GENERATORS AUTOSTARTED AND ENERGIZED VITAL BUSES 1A3 AND |
| 1A4, AT 0134CDT. SHUTDOWN COOLING WAS LOST FOR APPROXIMATELY [TWO] 2 |
| MINUTES AND RESTORED WHEN THE DIESEL GENERATORS WERE PLACED ON THE BUS. |
| SHUTDOWN COOLING TEMPERATURE INDICATED [ZERO] 0 DEGREES FAHRENHEIT |
| TEMPERATURE RISE IN THE [TWO] 2 MINUTES THAT SHUTDOWN COOLING WAS LOST. |
| WHEN THE EMERGENCY PLAN WAS ENTERED, VITAL BUSES WERE ALREADY RE-ENERGIZED. |
| AN ALERT WAS REPORTED UNDER EAL 4.3 BUT NOT DECLARED. OFFSITE POWER WAS |
| ALWAYS AVAILABLE, AND AS OF THIS TIME IS ON VITAL BUS 1A3." |
| |
| OFFSITE POWER WAS RESTORED TO BUSES 1A3 AND 1A4 AT 0159CDT AND 0209CDT, |
| RESPECTIVELY. INITIAL RCS TEMPERATURE WAS 103 DEGREES FAHRENHEIT. SHUTDOWN |
| COOLING TRAIN "A" WAS PLACED IN-SERVICE TO REPLACE THE OPERATING TRAIN "B" |
| WHICH WAS DEENERGIZED. THE ELECTRICAL MAINTENANCE HAS LOOKED AT |
| TRANSFORMERS INSIDE AND OUTSIDE THE PLANT AND FOUND NO APPARENT FAILURE. |
| |
| THE LICENSEE NOTIFIED BOTH STATE AND LOCAL AGENCIES AND WILL INFORM THE NRC |
| RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36348 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FEDERAL BUREAU OF INVESTIGATION |NOTIFICATION DATE: 10/26/1999|
|LICENSEE: UNKNOWN |NOTIFICATION TIME: 10:08[EDT]|
| CITY: WASHINGTON REGION: 1 |EVENT DATE: 10/26/1999|
| COUNTY: STATE: DC |EVENT TIME: 09:30[EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 10/26/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DAVID LEW R1 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: GARTEN | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE FBI REPORTED A STOLEN TROXLER GAUGE WAS RECOVERED. |
| |
| THE FBI RECOVERED A STOLEN TROXLER GAUGE MODEL 3411-B SERIAL # 4311 ON SOUTH |
| CAPITAL ST IN WASHINGTON D.C. IT WAS RECOVERED FROM AN INDIVIDUAL THAT WAS |
| TRYING TO SELL IT. |
| THE DEVICE APPEARED TO BE INTACT, BUT THE PLASTIC CASE WAS OPEN. THE |
| READINGS MEASURED WAS 1.18 MILLIREM AND THE PAGER-S READ 8. THE FBI HAS THE |
| DEVICE IN ITS POSSESSION. |
| |
| *** UPDATE ON 10/26/99 @ 1104 BY NELSON TO GOULD *** |
| |
| THE FBI HAVE LOCATED THE OWNER OF THE STOLEN TROXLER GAUGE. EBA ENGINEERING |
| OF BALTIMORE, MD. IS THE OWNER OF THE DEVICE AND THEY BELIEVE IT WAS STOLEN |
| LAST NIGHT. |
| THE FBI HAS NOT YET RETURNED THE DEVICE TO THE OWNER. |
| |
| NOTIFIED REG 1 RDO(LEW) AND NMSS EO(HICKEY) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 36349 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MERCY HOSPITAL |NOTIFICATION DATE: 10/26/1999|
|LICENSEE: MERCY HOSPITAL |NOTIFICATION TIME: 11:00[EDT]|
| CITY: PORT HURON REGION: 3 |EVENT DATE: 10/26/1999|
| COUNTY: STATE: MI |EVENT TIME: 03:45[EDT]|
|LICENSE#: 211563801 AGREEMENT: N |LAST UPDATE DATE: 10/26/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MIKE JORDAN R3 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SMITH | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION AT THE MERCY HOSPITAL IN PORT HURON, MI |
| |
| A PATIENT AT THE HOSPITAL WAS UNDERGOING TREATMENT WITH A WIRE OF IRIDIUM |
| SEEDS(33 @ .923 MILLICURIES/SEED) INSERTED INTO A CATHETER, HOWEVER, THE |
| WIRE CAME OUT PRIOR TO THE TIME IT WAS SCHEDULED TO BE REMOVED. TREATMENT |
| TIME WAS TO BE 48 HOURS BEGINNING @ 1015 ON 10/25/99, HOWEVER THE WIRE |
| CAME OUT @ 0330 ON 10/26/99 RESULTING IN THE PATIENT ONLY RECEIVING 36% TO |
| 38% OF HIS PRESCRIBED TREATMENT. THE NURSE RESPONDED TO THE PATIENT'S CALL |
| WITHIN A MINUTE AND REMOVED THE SOURCES FROM THE PROXIMITY OF THE PATIENT |
| AND CALLED THE AUTHORIZED USER AND THE RSO. HOWEVER ,WHEN THE NURSE ENTERED |
| THE PATIENT'S ROOM, SHE FOUND THE PATIENT HOLDING THE WIRE IN HIS HANDS. |
| THEY CALCULATED THE DOSE TO THE PATIENT'S FINGERS TO BE 5 RADS. THE |
| PATIENT'S PHYSICIAN HAS NOT YET BEEN NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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: 10/26/1999|
| 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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36351 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 10/26/1999|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 16:44[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 08/25/1999|
+------------------------------------------------+EVENT TIME: 10:20[CDT]|
| NRC NOTIFIED BY: K HILL |LAST UPDATE DATE: 10/26/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING (RCIC) DECLARED INOPERABLE ON 08/26/99 |
| |
| The licensee is reviewing events from the past couple of years in which RCIC |
| was declared inoperable. Control Room personnel were notified they should |
| have reported events to the NRC over the last couple of years(per |
| 10CFR50.72(b)(2)(iii)(D)) when RCIC was declared inoperable. |
| |
| On 08/25/99 at 1020CT, while conducting post maintenance testing to return |
| Unit 2 RCIC to operable status, the RCIC system turbine tripped on |
| overspeed. RCIC was subsequently repaired and made operable on 08/26/99 at |
| approximately 1500 hours. All Emergency Core Cooling Systems were fully |
| operable during the time period RCIC was inoperable. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36352 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/26/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 20:37[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/26/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 03:59[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/26/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MIKE JORDAN R3 |
| DOCKET: 0707002 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM MCCLEERY | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| RECEIVED A CASCADE AUTOMATIC DATA PROCESSING (CADP) SMOKEHEAD ALARM. |
| |
| On 10/26/99 at 0359 hours, operations personnel received a CADP smokehead |
| alarm for system 31-3 smoke head S-16 located in Cascade Facility X-330. A |
| valving operation was in progress when the alarm was received. Operations |
| immediately stopped the operation and isolated the piping. Radiological air |
| samples and visual observations did not indicate a release of Uranium |
| Hexafluoride. Smokehead detector can be activated by dust, smoke , Uranium |
| Hexafluoride, etc. |
| |
| A graphic plot of the firing voltage (voltage drop) from the CADP system of |
| the alarming smokehead gave indication that the CADP system received a valid |
| signal. The certificate holder does not know what activated the smokehead. |
| |
| |
| This is reportable as an activation of a Q safety system per Safety Analysis |
| Report (SAR) section 6.9 table 6.9-1. |
| |
| There was no loss of hazardous/radioactive material or |
| radioactive/radiological contamination exposure as a result of this event. |
| |
| The NRC Resident Inspector was notified of this event by the certificate |
| holder. |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36353 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 10/26/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 22:51[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 10/26/1999|
+------------------------------------------------+EVENT TIME: 19:20[CDT]|
| NRC NOTIFIED BY: MARSHALL FUNKHOUSER |LAST UPDATE DATE: 10/26/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE SPRAY (HPCS) DECLARED INOPERABLE DUE TO ITS MINI FLOW |
| VALVE FAILING TO FULLY OPEN. |
| |
| |
| Clinton Power Station is presently performing a planned Division 3 (HPCS |
| Diesel ) outage. The plant has been in a limited condition for operation |
| allowed by Technical Specifications for this outage since 0230 CT on |
| 10/26/99. At 1920 hours on 10/26/99 during performance of a High Pressure |
| Spray System Surveillance the HPCS Minimum Flow Valve (1E22-F012) failed to |
| operate properly. During an open stroke of the Minimum Flow valve, power |
| was lost due to a breaker trip and the valve failed to fully open. This |
| valve provides a minimum amount of flow through the system to ensure that |
| the pump does not overheat. The Plant's Technical Specification provides |
| allowances for this condition but 10CFR50.72(b)(2)(iii)(D) requires that a |
| component failure that could have prevented an independent safety system |
| from performing its function be reported. This system may have failed to |
| perform its safety function due to the failure of this valve, thus, this |
| report is being made. The licensee entered Technical Specification 3.5.1 |
| (14 days Limiting Condition of Operation). The Reactor Core Isolation |
| Cooling and all other Emergency Core Cooling Systems are fully operable if |
| needed. The Electrical Grid is Stable and Division 1 and 2 Emergency Diesel |
| Generators a fully operable. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021