Event Notification Report for June 28, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/25/1999 - 06/28/1999
** EVENT NUMBERS **
35790 35856 35860 35861 35862 35863 35864 35865 35866 35867 35868 35869
35870 35871 35872 35873 35874
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35790 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/03/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:44[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/02/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:30[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/25/1999|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |DAVID HILLS R3 |
| DOCKET: 0707001 |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: THOMAS WHITE | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THREE SPRINKLER SYSTEMS DECLARED INOPERABLE DUE TO CORRODED HEADS (24-hour |
| report) |
| |
| The following text is a portion of a facsimile received from Paducah: |
| |
| "On 06/02/99 at 1630 CDT, the Plant Shift Superintendent (PSS) was notified |
| that numerous sprinkler heads were corroded, affecting 16 sprinkler systems |
| in C-337 and one system in C-333, such that the ability of the sprinklers to |
| flow sufficient water was called into question. Subsequently, these |
| sprinkler systems were declared inoperable, and TSR-required actions |
| establishing roving fire patrols were initiated. This deficiency was |
| detected during scheduled system inspections conducted by Fire Protection |
| personnel. Currently, functionality of the sprinkler heads has not been |
| fully evaluated by Fire Protection personnel, and the remaining cascade |
| buildings are currently being inspected, and if necessary, this report will |
| be updated to identify any additional areas. |
| |
| "It has been determined that this event is reportable under |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to |
| function as designed." |
| |
| The NRC resident inspector has been notified of this event. |
| |
| ******************** UPDATE RECEIVED AT 1022 EDT ON 06/04/99 FROM CAGE TO |
| TROCINE ******************* |
| |
| The following text is a portion of a facsimile received from Paducah: |
| |
| "Two sprinkle heads on system D-1 in C-337 and two sprinkler heads on system |
| 27 in C-335 were identified to also be corroded. These were identified to |
| the PSS on 06/03/99 at 1600 CDT and 1601 CDT, respectively, and determined |
| to require an update to this report by the PSS. |
| |
| "It has been determined that this event is reportable under |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to |
| function as designed." |
| |
| Paducah personnel notified the NRC resident inspector of this update. The |
| NRC operations officer notified the R3DO (Hills) and NMSS EO (Combs). |
| |
| *********** UPDATE RECEIVED AT 2152 EDT ON 06/17/99 FROM WALKER TO POERTNER |
| *********** |
| |
| The following text is a portion of a facsimile received from Paducah: |
| |
| "Three sprinkler heads on system C-15 and five sprinkler heads on system B-8 |
| in C-333 were identified to also be corroded. The PSS was notified of this |
| condition at 1300 CDT on 06/17/99 and determined that an update to this |
| report was required." |
| |
| "It has been determined that this event is reportable under |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to |
| function as designed." |
| |
| Paducah personnel notified the NRC resident inspector of this update. The |
| NRC operations officer notified the R3DO (Madera). |
| |
| * * * UPDATE AT 1440 ON 06/18/99 FROM UNDERWOOD TAKEN BY STRANSKY * * * |
| |
| "Two sprinkler heads on system C-15 and one sprinkler head on system B-8 in |
| C-333 were identified to have corrosion. The PSS was notified of this |
| condition at 1350 CDT on 06/18/99. The area of the fire patrol for system |
| C-15 was expanded to include the two heads identified as corroded. The one |
| head on system B-8 was in the area already being patrolled. The PSS |
| determined that an update to this report was required." |
| |
| The NRC resident inspector has been informed of this update. The NRC |
| operations officer notified R3DO (Madera). |
| |
| * * * UPDATE 1315 6/25/1999 FROM WALKER TAKEN BY STRANSKY * * * |
| |
| "Two sprinkler heads on system D-8 and three sprinkler heads on system D-7 |
| in C-337 were identified to have corrosion. The PSS was notified of the |
| condition on system D-8 at 0125 on 6/25/99 and at 1019 on 6/25/99 for system |
| D-7. Both systems were immediately declared inoperable and LCO fire patrol |
| actions were implemented. It was determined that an update to this report |
| was required." |
| |
| The NRC resident inspector has been informed of this update. Notified R3DO |
| (Jordan). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 35856 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: U.S. VETERANS ADMINISTRATION |NOTIFICATION DATE: 06/24/1999|
|LICENSEE: DURHAM VA HOSPITAL |NOTIFICATION TIME: 15:00[EDT]|
| CITY: DURHAM REGION: 2 |EVENT DATE: 05/28/1999|
| COUNTY: STATE: NC |EVENT TIME: 12:00[EDT]|
|LICENSE#: 32-01134-01 AGREEMENT: Y |LAST UPDATE DATE: 06/25/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |AL BELISLE R2 |
| |FRED COMBS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: LYNN McGUIRE | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF IODINE-125 SEEDS INTO SANITARY SEWER |
| |
| "On May 28, 1999, two I-125 sources, with a combined activity of 0.584 mCi, |
| were lost from the Medical Center. The seeds had been implanted into a |
| patient's prostate earlier in the day. The patient had been instructed to |
| save his urine so that any seeds passed in the urine could be recovered. An |
| instruction sheet was posted on the door, directing that all urine, trash |
| and linen be saved, and nurses had been trained for the procedure. A nurse |
| called nuclear medicine to report that two seeds were in the urine |
| container. When nuclear medicine personnel arrived to recover the seeds, |
| the urine had been flushed into the sanitary sewer by another staff member |
| on the floor. |
| |
| "The toilet and urine container were surveyed with a portable low-energy |
| gamma detector, and no residual activity was detected. The sources are |
| presumed to have gone into the sewer, and assuming the seeds remain covered |
| by water, no significant exposure is expected to any individual member of |
| the public. On June 1, 1999, the loss of the sources was reported by phone |
| to the VA National Health Physics Program. |
| |
| "In order to prevent recurrence of this type of incident, the nurses on ward |
| 7A have been retrained in the proper procedures. In the future, implant |
| patient rooms will be posted with larger signs saying 'hold urine, trash, |
| linen'." |
| |
| * * * UPDATE AT 0950 EDT ON 6/25/99 BY KELLY MAYO TO FANGIE JONES * * * |
| |
| Corrected reporting criteria from 10 CFR 20.2201(a)(1)(i) to 10 CFR |
| 20.2201(a)(1)(ii) as the activity was more than 10 times the limit, but less |
| than 1000 times the limit. Notified the R2DO (Al Belisle) and NMSS (Larry |
| Camper).. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35860 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 06/25/1999|
| UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 14:32[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 06/25/1999|
+------------------------------------------------+EVENT TIME: 10:23[CDT]|
| NRC NOTIFIED BY: RICK PEARSON |LAST UPDATE DATE: 06/25/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - CONTROL ROOM VENTILATION SYSTEM INOPERABLE DUE TO A BROKEN DOOR LATCH |
| MECHANISM - |
| |
| AT 1023 CDT ON 06/25/99, WITH BOTH UNITS AT 100% POWER, THE LICENSEE |
| DISCOVERED THAT PERSONNEL ENTRY DOOR #158 TO CONTROL ROOM CHILLER ROOM #122 |
| HAD A BROKEN LATCH MECHANISM ON IT. THIS CONSTITUTES A BREACH OF THE |
| CONTROL ROOM SPECIAL VENTILATION SYSTEM AND THUS, BOTH TRAINS OF THE CONTROL |
| ROOM SPECIAL VENTILATION SYSTEM ARE INOPERABLE (TECH SPEC 3.13.A.1). |
| |
| AT 1121 CDT ON 06/25/99, PLANT TECHNICIANS REPAIRED THE BROKEN DOOR LATCH |
| MECHANISM AND DECLARED THE VENTILATION SYSTEM OPERABLE. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35861 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 06/25/1999|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 15:23[EDT]|
| RXTYPE: [2] GE-4 |EVENT DATE: 06/25/1999|
+------------------------------------------------+EVENT TIME: 14:30[EDT]|
| NRC NOTIFIED BY: STEVE MAREK |LAST UPDATE DATE: 06/25/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |MIKE JORDAN R3 |
|10 CFR SECTION: |ROBERT DENNIG NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |JOSEPH GIITTER IRO |
|AENS 50.72(b)(1)(v) ENS INOPERABLE |CANUPP FEMA |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 97 Power Operation |97 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED DUE TO LOSS OF TELEPHONE SERVICE |
| |
| "At 1430, Fermi 2 determined that the Emergency Notification System (ENS) |
| phones were not available. The local telephone company notified Fermi 2 that |
| an offsite fiber optic cable was cut. Additionally, local phone service to |
| Monroe County, including the Monroe County Sheriffs Department is |
| unavailable. Security radio communication to the Monroe County Sheriff is |
| available and has been verified. RERP phone service to locations outside |
| Monroe County is available. |
| |
| "This report is being made in accordance with 10CFR50.72(b)(1)(v), as an |
| event that results in a major loss of emergency response assessment |
| capability, or communications capability. |
| |
| "At 1508, an Unusual Event was declared due to notification that the |
| Emergency Call Out System (ECOS) may also be impaired, due to the loss of |
| local phones." |
| |
| The NRC resident inspector has been informed of this notification. |
| |
| * * * UPDATE 1844 6/25/99 FROM MAREK TAKEN BY STRANSKY * * * |
| |
| The Unusual Event was terminated at 1838 after the ENS and offsite telephone |
| service were restored. The licensee will inform the NRC resident inspector |
| of this update. Notified R3DO(Jordan), NRR EO (Hannon), FEMA (Sullivan). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35862 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ABB COMBUSTION ENGINEERING |NOTIFICATION DATE: 06/25/1999|
|LICENSEE: ABB COMBUSTION ENGINEERING |NOTIFICATION TIME: 16:34[EDT]|
| CITY: WINDSOR REGION: 1 |EVENT DATE: 06/25/1999|
| COUNTY: STATE: CT |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 06/25/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GLENN MEYER R1 |
| |VERN HODGE (via fax) NRR |
+------------------------------------------------+ |
| NRC NOTIFIED BY: IAN RICKARD | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT REGARDING ABB 4kV CIRCUIT BREAKERS |
| |
| The following text is excerpted from a facsimile received in the Operations |
| Center: |
| |
| "The defect concerns ABB 1200A 4KV Vacuum Breakers delivered to Baltimore |
| Gas and Electric Company's Calvert Cliffs Nuclear Power Plant. Specifically, |
| the defect concerns the breaker performing a trip free operation when a |
| close signal is received by the breaker. This defect results in the breaker |
| failing to remain in the closed position. The defect could lead to |
| non-conservative failure of not starting certain plant equipment upon demand |
| such as an Emergency Core Cooling Pump." |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35863 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 06/25/1999|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 18:52[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 06/25/1999|
+------------------------------------------------+EVENT TIME: 09:30[CDT]|
| NRC NOTIFIED BY: RICK HUBBARD |LAST UPDATE DATE: 06/27/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOSEPH TAPIA R4 |
|10 CFR SECTION: | |
|BAE1 20.2202(b)(1) PERS OVEREXPOSURE | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| PERSONNEL OVEREXPOSURE |
| |
| A worker received internal contamination resulting in an estimated total |
| effective dose equivalent (TEDE) of 14.5 rem (145 mSv). The individual had |
| been involved in decontamination activities on the 1974' elevation of the |
| auxiliary building, in the valve gallery of the Boron Thermal Regeneration |
| System room. Upon exiting the area, significant contamination was detected |
| on the individual's face (up to 80,000 dpm on the right side of the face). |
| The individual was decontaminated and a whole body count was performed. The |
| whole body count indicated the presence of cobalt-58 contamination in the |
| individual's gastrointestinal tract. Whole body counts were given to other |
| individuals who had been working in the same area, but no additional |
| internal contamination was discovered. |
| |
| The licensee has issued a stop work order for all work areas with |
| contamination levels in excess of 50,000 dpm, except those with specific |
| approval from the Radiation Protection Manager. The licensee is also |
| forming an Incident Investigation Team to determine the root cause of this |
| event. The NRC resident inspector has been informed of this event by the |
| licensee. |
| |
| |
| * * * UPDATE AT 0920 ON 6/26/99, BY HUBBARD TAKEN BY WEAVER * * * |
| The licensee has notified the State of this event and also issued a press |
| release. HOO notified R4DO (Tapia). |
| |
| * * * COMMISSIONERS ASSISTANTS BRIEFING 2000 6/26/99 * * * |
| |
| A Commissioners Assistants briefing was held regarding this event. |
| Participants: NRR (Donahue, Richards, Zwolinski), Region IV (Brockman, |
| Brush, Hackney, Good, Ricketson, Henderson, Graves-briefer), NMSS (Cool), |
| OCA (Madden), OPA (Gilliland), OSP (Sollenberger), EDO (Knapp, Lange), IRO |
| (Giitter), Chm Jackson (Johnson), Comm Merrifield (McCabe), Comm Dicus |
| (Lubenau), Comm McGaffigan (Crockett), Comm Diaz (Castleman). |
| |
| * * * RETRACTED AT 1751 EDT ON 6/27/99 BY RICK HUBBARD TO FANGIE JONES * * |
| * |
| |
| Further reviews of this event identified a significant error in the |
| original dose calculations which were the basis of the report. The error |
| was in the use of a software generated activity rather than actual activity, |
| a matter of using the wrong column's information in the calculations. Using |
| the correct value, the internal exposure is estimated to be 2 mRem. The |
| external exposure received by the individual on that work activity was 5 |
| mRem. The assigned total effective dose equivalent (TEDE) is a combination |
| of the internal and external exposures. Therefore, when corrected, the |
| TEDE is estimated to be approximately 7 mRem versus the 14.5 Rem reported on |
| June 25, 1999. |
| |
| The exposure of the individual involved in the June 25 decontamination |
| evolution was well below regulatory limits and, therefore, does not meet the |
| reporting requirements. Therefore, Event Notification # 35863 is being |
| retracted. |
| |
| The licensee notified the NRC Resident Inspector for the Wolf Creek |
| Generating Station and will also notify the State of Kansas and the media. |
| The Headquarters Operations Officer notified the R4DO (Joseph Tapia). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35864 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 06/25/1999|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 18:57[EDT]|
| RXTYPE: [3] CE |EVENT DATE: 06/25/1999|
+------------------------------------------------+EVENT TIME: 17:45[CDT]|
| NRC NOTIFIED BY: ARTHUR WEMETT |LAST UPDATE DATE: 06/25/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOSEPH TAPIA R4 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FAILURE OF LICENSEE TO SUBMIT CHANGES TO LICENSING BASIS FOR NRC REVIEW |
| |
| On 6/25/99, the NRC notified the licensee that the use of equipment failure |
| probabilities (TORMIS) in the assessment of tornado and missile effects on |
| the emergency feedwater (EFW) system constitutes a change to the licensing |
| and design bases of the system. Such changes to the licensing and design |
| bases constitute an Unreviewed Safety Question (USQ) and require formal NRC |
| review and approval in accordance with 10 CFR 50.90. The licensee has |
| decided not to contest the conclusion by the NRC. |
| |
| An engineering evaluation had previously been performed to postulate the |
| effects of tornado winds and missiles on the EFW pump turbine steam supply |
| piping and steam exhaust stack. The evaluation concluded that the results |
| were acceptable, based on criteria provided in NRC Regulatory Guide 1.117. |
| Based upon this evaluation, the licensee has concluded that the EFW system |
| is operable with respect to its design basis functions, including the |
| effects of tornado winds and missiles. |
| |
| The licensee plans to submit a formal license amendment request in |
| accordance with 10 CFR 50.90 to incorporate the use of TORMIS. The NRC |
| resident inspector has been informed of this notification by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35865 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 06/25/1999|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 22:30[EDT]|
| RXTYPE: [2] GE-4 |EVENT DATE: 06/25/1999|
+------------------------------------------------+EVENT TIME: 19:28[EDT]|
| NRC NOTIFIED BY: R. PIZARRO |LAST UPDATE DATE: 06/25/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+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 97 Power Operation |97 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HPCI SYSTEM DECLARED INOPERABLE |
| |
| The licensee declared the high pressure coolant injection (HPCI) system |
| inoperable after the manual/automatic flow controller (E41-R614) was found |
| to be indicating full downscale. The cause of the problem is currently |
| under investigation. The licensee entered Technical Specification 3.5.1.c, |
| and verified that all other emergency core cooling systems are operable. |
| Although the HPCI flow controller would be unable to automatically control |
| system flow, the licensee believes that operators would be able to control |
| system flow manually, if needed. |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35866 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 06/25/1999|
| UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 23:08[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/25/1999|
+------------------------------------------------+EVENT TIME: 20:30[EDT]|
| NRC NOTIFIED BY: DAN ETHERIDGE |LAST UPDATE DATE: 06/25/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN R3 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| EMERGENCY DIESEL GENERATOR DECLARED INOPERABLE |
| |
| "The Diesel Generator Fuel Oil System is designed to provide the required |
| amount of diesel fuel to operate the EDGs on each unit for a minimum of |
| seven days at the full load capacity of the generators. Two fuel oil |
| transfer pumps are provided for each EDG to transfer diesel fuel from the |
| storage tank to the fuel oil day tank. From each day tank, the fuel oil |
| flows by gravity into the suction of the engine-driven fuel pump. The pump |
| provides nine gpm at 35 psig and discharges through a duplex fuel oil filter |
| into the two fuel oil supply manifolds. |
| |
| "Some of the fuel oil which flows from the supply manifold into the |
| injection pump is not delivered to the spray nozzle. This excess fuel oil |
| circulates through the injection pump, cooling the injection pump, and |
| providing lubrication for the fuel oil side of the pump. The fuel oil then |
| flows to the return manifold. To maintain a fixed pressure in the supply |
| manifold, a relief valve at the end of each supply manifold (SV-200 set at |
| 25 psig) bypasses fuel oil to the return manifold. |
| |
| "On 6/25/99, during routine inspection of the fuel oil lines, it was |
| discovered that SV-200 on one of the Unit 1 EDGs was installed backwards, |
| effectively blocking the safety valve from relieving excess pressure on the |
| supply manifold. This configuration may have existed since initial |
| construction. The EDG has been operated successfully many times with this |
| condition, but uncertainty about the ability to operate for 7 days, |
| especially at low loads, has caused the EDG to be declared inoperable and |
| prompted this 4 hour NRC notification. The EDG remains available and will be |
| repaired at the earliest opportunity." |
| |
| The licensee will inform the NRC resident inspector of this notification. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35867 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 06/26/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 05:28[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/26/1999|
+------------------------------------------------+EVENT TIME: 04:03[EDT]|
| NRC NOTIFIED BY: DOUGLAS AMTSFIELD |LAST UPDATE DATE: 06/26/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GLENN MEYER R1 |
|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
+------------------------------------------------------------------------------+
| HPCI INOPERABLE |
| |
| On 6-26-99, at 0403 the unit 2 HPCI System was declared inoperable following |
| performance of a routine test on the HPCI drain pot orifice. The purpose of |
| the test is to verify flow through the HPCI turbine exhaust drain pot |
| discharge line flow orifice. At the time of the failure HPCI was operable. |
| The HPCI system was conservatively declared inoperable due to the potential |
| for the exhaust line to fill. The licensee notified the NRC resident |
| inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35868 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/26/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 10:44[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/26/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 08:30[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/26/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MIKE JORDAN R3 |
| DOCKET: 0707002 | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KURT SISLER | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NOTIFICATION OF ANOTHER FEDERAL AGENCY |
| |
| The licensee notified the DOE of an event in the X-705 building annex |
| cylinder cleaning area. While attempting to clean an empty 8" cylinder it |
| was discovered that the cylinder would not fit into the cadmium shield. It |
| was later discovered that the NCSA had been based on a cylinder design which |
| was slightly smaller than the older cylinder which caused the problem. A |
| new NCSA will be performed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35869 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 06/26/1999|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 13:18[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 06/26/1999|
+------------------------------------------------+EVENT TIME: 10:08[EDT]|
| NRC NOTIFIED BY: BLAIR |LAST UPDATE DATE: 06/26/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KURT COWGILL R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| EDG STARTED AND LOADED DUE TO LOSS OF AUXILIARY TRANSFORMER |
| |
| At 1008, the '1B' 230 kV auxiliary transformer failed for unknown reasons. |
| The '1A' emergency diesel generator (EDG) automatically started and loaded |
| to its associated 4kV emergency bus. The unit is currently stable at 100% |
| power. The licensee stated that EDG will remain loaded to its emergency bus |
| until the auxiliary transformer can be restored to service. The NRC |
| resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35870 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/26/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:49[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/25/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 20:30[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/26/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MIKE JORDAN R3 |
| DOCKET: 0707002 |ROBERT PIERSON NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KURT SISLER | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 REPORT |
| |
| "ON 6/25/99 PLANT PERSONNEL PERFORMING A WALKDOWN OF X-744L (STOREROOM) TO |
| ENSURE COMPLIANCE WITH NCSA-PLANT046 'CONTAMINATED METAL' DISCOVERED PALLETS |
| OF VACUUM PUMPS (3-4 pumps) STACKED FOUR TO A PALLET ON STORAGE RACKS WITHIN |
| A CONTAMINATION STORAGE AREA. THE PUMPS ARE CONTAMINATED BUT THERE IS NO |
| DOCUMENTATION IMMEDIATELY AVAILABLE IDENTIFYING THE URANIUM CONCENTRATION IN |
| THESE PUMPS. THIS BUILDING HAS PREVIOUSLY BEEN SCANNED BY THE APPLIED |
| NUCLEAR TECHNOLOGY GROUP FOR NDT ANALYSIS OF THE MATERIAL. WITHOUT THIS |
| DOCUMENTATION READILY AVAILABLE THE NCSA REQUIRES THE MATERIAL TO BE SPACED |
| AT A MINIMUM TWO FOOT EDGE-TO-EDGE SPACING. THIS IS A VIOLATION OF ONE |
| CONTROL (SPACING) OF THE DOUBLE CONTINGENCY MATRIX. THE OTHER CONTROL VOLUME |
| WAS MAINTAINED." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35871 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/26/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 19:04[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/26/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 05:33[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/26/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MIKE JORDAN R3 |
| DOCKET: 0707002 |ROBERT PIERSON NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DALE NOEL | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MOTOR STOP BUTTON FAILED TO FUNCTION AS DESIGNED |
| |
| "ON 6/26/99 AT 0533 HOURS, THE X-333 PROCESS BUILDING AREA CONTROL ROOM |
| (ACR) #1 MOTOR STOP BUTTON FAILED TO FUNCTION AS DESIGNED WHEN CALLED UPON |
| TO SHUTDOWN MOTORS ON CELL 33-5-10 (CASCADE OPERATIONAL MODE Ill). THIS |
| REPRESENTS THE FAILURE OF TECHNICAL SAFETY REQUIREMENT (TSR) SURVEILLANCE |
| 2.2.3.14.3 FOR CASCADE D.C. CONTROL POWER WHICH STATES: 'UTILIZE THE ACR |
| MOTOR STOP BUTTON FOR EACH SCHEDULED CELL TRIP. MONITOR EXPECTED CELL BLOCK |
| VALVE CLOSURE AND ANY RECYCLE VALVE ACTUATION.' OPERATIONS PERSONNEL |
| IMMEDIATELY UTILIZED AN ALTERNATE MEANS LOCATED AT THE CELLS LOCAL CONTROL |
| CENTER (LCC) TO TRIP CELL 33-5-10 MOTORS. |
| |
| "THIS EVENT IS REPORTABLE DUE TO A SAFETY SYSTEM COMPONENT (SSC) REQUIRED BY |
| THE TSR NOT BEING AVAILABLE OR OPERABLE AND NO REDUNDANT EQUIPMENT WAS |
| AVAILABLE TO PERFORM THE REQUIRED SAFETY FUNCTION. |
| |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35872 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 06/27/1999|
| UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 14:00[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/27/1999|
+------------------------------------------------+EVENT TIME: 11:00[CDT]|
| NRC NOTIFIED BY: ROBERT BRINKLEY |LAST UPDATE DATE: 06/27/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOSEPH TAPIA R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR PROTECTION SYSTEM ACTUATION RESULTING IN REACTOR TRIP |
| |
| The unit had a reactor trip from OTDeltaT, all control rods fully inserted. |
| Auxiliary Feedwater, an Engineered Safety Features (ESF) system, |
| automatically started on low steam generator level and feedwater isolation, |
| as expected. The pressurizer power operated relief valves lifted on the |
| reactor trip and then reseated. Also, some steam generator safeties lifted |
| momentarily and reseated, the steam dumps to the condenser are operating to |
| remove excess energy. The plant is stable in Hot Standby. |
| |
| All systems functioned as required, the only unexpected action was the trip |
| of both main feedwater pumps on overspeed during the transient. The cause |
| of the reactor trip is being investigation, a turbine trip is suspected. |
| The trip of the feed pumps is also under review. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35873 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 06/27/1999|
| UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 18:21[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 06/27/1999|
+------------------------------------------------+EVENT TIME: 16:55[CDT]|
| NRC NOTIFIED BY: VAUDY HOLLEY |LAST UPDATE DATE: 06/27/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| LOSS OF OFFSITE COMMUNICATION SYSTEM - TONE ALERT RADIO |
| |
| After thunderstorms moved through the area of the plant, the licensee |
| discovered that communications with the meteorological tower had been lost |
| and the tone alert radio system was unavailable for greater than 15 minutes, |
| part of the public communication (warning) system. |
| |
| Workers have been called in to investigate and repair the systems that have |
| been lost. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35874 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 06/28/1999|
| UNIT: [] [2] [] STATE: GA |NOTIFICATION TIME: 03:55[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/28/1999|
+------------------------------------------------+EVENT TIME: 03:00[EDT]|
| NRC NOTIFIED BY: FRANK GORLEY |LAST UPDATE DATE: 06/28/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM ON LOW REACTOR WATER LEVEL |
| |
| The reactor automatically scrammed on low reactor vessel water level because |
| of maintenance activities on the 'B' level keep fill system. Operators |
| venting the keep fill system unintentionally vented the 'B' reference leg |
| because the isolation valve between the two system is apparently leaking. |
| This venting caused level instruments using the 'B' reference leg to |
| indicate high. The mismatch on level indicators caused the feed system to |
| switch to the 'B' leg (which happened to be the failed system). This |
| resulted in a decrease in feed flow and an actual decrease in reactor vessel |
| water level. |
| |
| The decrease in reactor water level caused a reactor scram and High Pressure |
| Coolant Injection (HPCI) initiation. Reactor Core Isolation Cooling (RCIC) |
| did not initiate because it uses the 'B' reference leg as an input. |
| All control rods fully inserted. The plant is stable in mode 3. Water |
| level has been restored to the normal band and is being maintained by the |
| feed system. The recirculating pumps are operating and no safety relief |
| valves lifted. The lowest indicated level was -45". |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021