Event Notification Report for June 7, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/04/1999 - 06/07/1999
** EVENT NUMBERS **
35686 35687 35790 35791 35792 35793 35794 35795 35796 35797 35798 35799
35800 35801 35802
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35686 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/06/1999|
| UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 18:44[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/06/1999|
+------------------------------------------------+EVENT TIME: 18:00[EDT]|
| NRC NOTIFIED BY: MARTIN |LAST UPDATE DATE: 06/04/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES LINVILLE R1 |
|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 Cold Shutdown |0 Cold Shutdown |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| VALVE FAILED LOCAL LEAK RATE TEST (LLRT). |
| |
| VALVE 3QSS*V4 IS A CHECK VALVE IN THE QUENCH SPRAY SYSTEM, AND THE CAUSE OF |
| THE LLRT FAILURE IS UNKNOWN AND BEING INVESTIGATED, BUT MOST LIKELY MAY BE |
| DUE TO VALVE DEGRADATION. WHEN THE RESULTS OF ITS LLRT WERE ADDED TO THE |
| OTHER CATEGORY "C" VALVES' RESULTS, THE TOTAL LEAKAGE EXCEEDED TECHNICAL |
| SPECIFICATION ALLOWABLE LIMITS OF 43 SCFH (TOTAL MEASURED CATEGORY "C" WAS |
| 335 SCFH); HOWEVER, THE TOTAL LEAKAGE OF EVERYTHING STILL DID NOT EXCEED THE |
| 0.6 La VALUE. CORRECTIVE ACTION WILL BE TO REPAIR THE VALVE PRIOR TO |
| STARTUP. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED ALONG WITH STATE, LOCAL AND OTHER |
| GOVERNMENT AGENCIES. |
| |
| * * * UPDATE 1134 5/13/99 FROM STEVE LAWHEAD TAKEN BY STRANSKY * * * |
| |
| Local leak rate testing of valve SIL*V6 (RHS Loop 1 Cold Leg Check Valve) |
| found the leakage to be excessive. This leakage, when combined with the |
| other known leakage, caused TS LCO 3.6.1.2.b to be exceeded. The TS |
| requires a combined leakage rate of less than 0.6 La for all penetrations |
| and valves subject to Type B and C tests, when pressurized to Pa. The NRC |
| resident inspector has been informed of this update. Notified R1DO |
| (Cowgill). |
| |
| * * * RETRACTION 1633 EDT ON 6/4/99 BY DALE BRODSKY TO FANGIE JONES * * * |
| |
| These conditions were conservatively reported as conditions outside the |
| unit's design basis. |
| |
| "A review has determined that the Combined Type B and C Leakage limit of |
| 0.60 La and the Enclosure Building (Secondary Containment) Bypass Leakage |
| limit of 0.042 La, (based upon ANSI/ANS 56.8-1994 and NUREG 1022, Rev. 1) |
| should be based upon the As-Found limit measured on a Minimum Pathway |
| Leakage Rate basis. Using this basis the measured total as-found leakage |
| does not exceed either limit. |
| |
| "These conditions are not reportable pursuant to 10 CFR 50.72(b)(1)(ii)(B) |
| as conditions outside the design basis, or pursuant to 10 CFR 50.72(b)(2)(i) |
| as events or conditions that may have resulted in an unanalyzed conditions |
| and therefore, the Immediate Notification for these conditions is |
| retracted." |
| |
| The licensee notified the NRC Resident Inspector. The Headquarters |
| Operations Officer notified the R1DO (Ronald Bellamy). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35687 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 05/06/1999|
| UNIT: [] [2] [] STATE: AL |NOTIFICATION TIME: 20:33[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 05/06/1999|
+------------------------------------------------+EVENT TIME: 16:14[CDT]|
| NRC NOTIFIED BY: NACOSTE |LAST UPDATE DATE: 06/04/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHRIS CHRISTENSEN R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 23 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE REACTOR WAS MANUALLY SCRAMMED FROM 23.5% POWER. |
| |
| DURING STARTUP FOLLOWING A REFUELING OUTAGE, THE UNIT EXPERIENCED A STEAM |
| LEAK ON THE INLET SIDE OF THE OFFGAS PREHEATER (ASME CLASS 2 PIPING). |
| TECHNICAL REQUIREMENTS MANUAL (TMR) SECTION 3.4.3 REQUIRES THAT THE |
| AFFECTED COMPONENT BE ISOLATED IMMEDIATELY, REQUIRING THAT THE MAIN STEAM |
| ISOLATION VALVES (MSIVs) BE CLOSED. THE MAIN TURBINE WAS TRIPPED FROM 23.5 |
| % POWER IN ANTICIPATION OF THE INSERTION OF A MANUAL SCRAM WHICH OCCURRED AT |
| 1614 CST. THE MANUAL SCRAM CAUSED REACTOR VESSEL WATER LEVEL TO GO BELOW |
| THE LOW SETPOINT LEVEL, WHICH GENERATED A REDUNDANT SCRAM SIGNAL AND |
| INITIATED THE PCIS ISOLATIONS OF GROUPS 2 (PRIMARY CONTAINMENT), 3 (RWCU), 6 |
| (SECONDARY CONTAINMENT), AND 8 (TIP SYSTEM). ALL RODS FULLY INSERTED, NO |
| ECCS INJECTION OCCURRED, AND NO RELIEF VALVES LIFTED. THE MSIVs WERE CLOSED |
| AT 1632. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT. |
| |
| * * * RETRACTED AT 1434 EDT ON 6/4/99 BY CHRIS VAUGHN TO FANGIE JONES * * * |
| |
| This event is retracted after review and determination that as a planned |
| manual reactor trip, it was not reportable under 10CFR50.72.2.ii per NUREG |
| 1022. |
| |
| The licensee notified the NRC Resident Inspector. The Headquarters |
| Operations Officer notified the R2DO (Kenneth Barr). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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: 06/04/1999|
| 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 1 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). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35791 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 06/04/1999|
| UNIT: [] [2] [] STATE: FL |NOTIFICATION TIME: 05:48[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 06/04/1999|
+------------------------------------------------+EVENT TIME: 03:13[EDT]|
| NRC NOTIFIED BY: JACK BREEN |LAST UPDATE DATE: 06/04/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KENNETH BARR 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 M/R Y 48 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - MANUAL REACTOR TRIP FROM 48% POWER DUE TO 4 CONTROL RODS DROPPING INTO THE |
| CORE - |
| |
| AT 0313 ON 06/04/99, WHILE PERFORMING TROUBLESHOOTING ACTIVITIES ON UNIT 2 |
| CONTROL ELEMENT DRIVE SYSTEM FOLLOWING A CONTROL ROD DROPPING INTO THE |
| REACTOR CORE ON 06/02/99 (REFER TO EVENT #35785), FOUR CONTROL ELEMENT |
| ASSEMBLIES (SHUTDOWN GROUP 'B' - SUBGROUP 21) FELL INTO THE REACTOR CORE FOR |
| UNKNOWN REASONS. CONTROL ROOM OPERATORS MANUALLY TRIPPED UNIT 2 FROM 48% |
| POWER. ALL CONTROL RODS INSERTED INTO THE CORE COMPLETELY. STEAM IS BEING |
| DUMPED INTO THE MAIN CONDENSER. UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). |
| |
| THE LICENSEE IS CONTINUING TO INVESTIGATE THE CAUSE(S) OF THE DROPPED |
| CONTROL RODS. |
| |
| THIS EVENT HAD NO EFFECT ON UNIT 1 WHICH IS OPERATING AT 100% POWER. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 35792 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: U.S. AIR FORCE |NOTIFICATION DATE: 06/04/1999|
|LICENSEE: U.S. AIR FORCE |NOTIFICATION TIME: 09:34[EDT]|
| CITY: Washington D.C. REGION: 1 |EVENT DATE: 06/04/1999|
| COUNTY: STATE: DC |EVENT TIME: 06:30[EDT]|
|LICENSE#: 42-23539-01AF AGREEMENT: N |LAST UPDATE DATE: 06/04/1999|
| DOCKET: 03028641 |+----------------------------+
| |PERSON ORGANIZATION |
| |RONALD BELLAMY R1 |
| |KENNETH BARR R2 |
+------------------------------------------------+LINDA HOWELL R4 |
| NRC NOTIFIED BY: MAJOR MITCH HICKS |FRED COMBS NMSS |
| HQ OPS OFFICER: LEIGH TROCINE |CHARLES MILLER IRO |
+------------------------------------------------+FRANK CONGEL IRO |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|IBDB 30.50(b)(4)(ii) DAMAGED LNM/CONTAINER | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF TWO 500- �Ci STRONTIUM-90 SOURCES DUE TO A HELICOPTER CRASH IN |
| FAYETTEVILLE, NORTH CAROLINA (24-HOUR REPORT) |
| |
| A representative from Bolling Air Force Base (located in Washington D.C.) |
| reported that a helicopter from Hurlburt Field (located in Mary Esther, |
| Florida) crashed at 2300 on 06/02/99 while performing a night training |
| exercise at Pope Air Force Base (located in Fayetteville, North Carolina). |
| Each helicopter blade contained an in-flight blade inspection system (IBIS) |
| source with 500 �Ci of Strontium-90, and it is currently believed that the |
| helicopter had four blades. Two of the four IBIS sources have been |
| identified and recovered by the pope Air Force Base Accident Response Team. |
| These devices have been bagged and will be checked for contamination. |
| Pending the completion of the crash investigation, the licensee plans to |
| search for the remaining IBIS sources with survey equipment. |
| |
| This event was reported to Bolling Air Force Base at 0630 on 06/04/99. |
| |
| Five individuals survived the crash, and there was one fatality. |
| |
| The limit referenced in 10 CFR Part 20, Appendix C, for Strontium-90 is 0.1 |
| �Ci. |
| |
| The licensee plans to notify the NRC Region 4 Office. (Call the NRC |
| Operations Center for a licensee contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35793 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 06/04/1999|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 12:35[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 06/04/1999|
+------------------------------------------------+EVENT TIME: 09:50[EDT]|
| NRC NOTIFIED BY: MITCH McCLUSKIE |LAST UPDATE DATE: 06/04/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RONALD BELLAMY R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ALTERNATE COOLING SYSTEM DECLARED INOPERABLE |
| |
| "Following a question raised by an NRC Resident Inspector at VY, an Event |
| Report was submitted due to a lack of sufficient analysis to determine if |
| procedural guidance was adequate for operation of the Alternate Cooling |
| System (ACS). VY declared the ACS inoperable at 2110 on 6/3/99 and entered |
| a 7 day LCO [3.5.d.3] per the plant Technical Specifications. Based on |
| further evaluation, Operations and Engineering Personnel concluded that |
| current VY procedures may not provide the specific information necessary to |
| ensure that ACS Design Bases 1 & 2 above, would have been met. Engineering |
| and Licensing evaluations of ACS design and performance requirements |
| continue. |
| |
| "VY is currently developing procedural enhancements that will ensure that |
| the operating crews are provided with the guidance necessary to ensure that |
| ACS would be operated in the manner necessary to achieve its safety design |
| bases. It is expected that the necessary procedural guidance will be |
| developed and issued prior to the |
| expiration of the cited 7 day LCO." |
| |
| The licensee notified the NRC Resident Inspector and the State of Vermont. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35794 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ARKANSAS DEPT OF HEALTH RAD CONTROL |NOTIFICATION DATE: 06/04/1999|
|LICENSEE: AQUATERRA, INC. |NOTIFICATION TIME: 12:51[EDT]|
| CITY: El DORADO REGION: 4 |EVENT DATE: 06/02/1999|
| COUNTY: STATE: AR |EVENT TIME: 18:00[CDT]|
|LICENSE#: LA-5382-L01 AGREEMENT: Y |LAST UPDATE DATE: 06/04/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA HOWELL R4 |
| |FRED COMBS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DAVID SNELLINGS | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT |
| |
| "Abstract: A Troxler gauge Model 3411 B (Serial # 9816) was run over and |
| damaged by a bulldozer at a construction site near El Dorado, Arkansas. The |
| gauge contained approximately 9 millicuries of Cesium-137 and 44 millicuries |
| of Americium-241: beryllium. The outer case of the gauge was damaged and |
| the source rod was bent. The licensee was working under reciprocity with a |
| Louisiana Radioactive Material License (LA-5382-L01). The licensee was able |
| to retrieve the gauge, assess the damage and return the gauge to the storage |
| location. A leak test was performed and Troxler Labs was notified. A |
| health physicist from the Arkansas Dept. of Health investigated the incident |
| on June 3, 1999. It was noted during investigation that the shutter was |
| partially opened resulting in doserate of 50 mR/hour at contact. Further |
| investigation is on going. |
| |
| "Arkansas License No: ARK-REC-232; Reciprocity Licensee: AQUATERRA, INC., |
| LA-5382L01, of PORT ALLEN, LA" |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 35795 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NORTH COUNTRY HOSPITAL |NOTIFICATION DATE: 06/04/1999|
|LICENSEE: NORTH COUNTRY HOSPITAL |NOTIFICATION TIME: 14:25[EDT]|
| CITY: Newport REGION: 1 |EVENT DATE: 02/04/1999|
| COUNTY: Orleans STATE: VT |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 06/04/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |RONALD BELLAMY R1 |
| |FRED COMBS NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: LARRY LABOR | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION AT NORTH COUNTRY HOSPITAL LOCATED IN NEWPORT, |
| VERMONT |
| |
| On 02/04/99, a medical misadministration occurred at North Country Hospital |
| located in Newport, Vermont. The physician prescribed a diagnostic test |
| involving 10 �Ci of Iodine-131, and a 305-�Ci dose of Iodine-131 was |
| administered. Subsequent review of the dose by a radiologist determined |
| that the literature search showed support for the dose received, and the |
| licensee stated that there were no anticipated adverse health affects. The |
| patient subsequently went to a tertiary medical center and received an |
| ablation therapy, and the 305-�Ci dose of Iodine-131 that was administered |
| on 02/04/99 at North Country Hospital was subtracted from the ablation dose |
| administered at the tertiary medical center. At this time, the licensee |
| does not plan to notify the patient. |
| |
| A Region 1 inspector (Thompson) was informed by the licensee on 06/03/99. |
| (Call the NRC Operations Center for a licensee contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35796 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 06/04/1999|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 16:03[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 06/04/1999|
+------------------------------------------------+EVENT TIME: 13:58[EDT]|
| NRC NOTIFIED BY: JIM PROPER |LAST UPDATE DATE: 06/04/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KENNETH BARR 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR TRIP DUE TO SPURIOUS SIGNAL DURING POWER RANGE CALIBRATION |
| |
| During the performance of power range calibration of N42, with a trip signal |
| in, a spurious signal from N43 was received which completed the 2 of 4 |
| coincidence for a reactor trip on high flux. The reactor tripped, all rods |
| inserted and all systems functioned as required. |
| |
| This event is being investigated and the plant will remain in Hot Standby |
| until the cause is determined and corrected. The plant is presently stable |
| with auxiliary feedwater supplying water to the steam generators and the |
| steam dumps exhausting to the main condenser. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35797 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 06/04/1999|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 17:04[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 06/04/1999|
+------------------------------------------------+EVENT TIME: 15:05[CDT]|
| NRC NOTIFIED BY: DAVE DEES |LAST UPDATE DATE: 06/04/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LINDA HOWELL R4 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO EXCESSIVE CHLORINE IN DISCHARGE |
| |
| The licensee notified the Kansas Department of Health and Environment due to |
| exceeding the residual limit of 0.2 ppm chlorine in the Circulating Water |
| discharge. The highest observed reading was 1.6 ppm. A mechanical failure |
| in the sodium hypochlorite feed pump is suspected. An investigation is in |
| progress and the system is isolated until corrected. |
| |
| The licensee notified the NRC Resident Inspector as well as the State of |
| Kansas and local county authorities. |
| |
| * * * UPDATE AT 2243 EDT ON 6/4/99 BY STEVE HEDGES TO FANGIE JONES * * * |
| |
| After subsequent evaluation of sodium hypochlorite release volumes, the |
| licensee determined that the release limits of 40 CFR 302 of 100 pounds was |
| exceeded. The calculated release was 1694 pounds. The licensee notified |
| the National Response Center (report # 486-281). |
| |
| The licensee notified the NRC Resident Inspector. The Headquarters |
| Operations Officer notified the R4DO (Linda Howell). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35798 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 06/04/1999|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 18:02[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 06/04/1999|
+------------------------------------------------+EVENT TIME: 17:17[EDT]|
| NRC NOTIFIED BY: JOHN SCHORK |LAST UPDATE DATE: 06/04/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RONALD BELLAMY 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR BUILDING EMERGENCY COOLING SYSTEM OPERABLE BUT DEGRADED |
| |
| "At 1717 hours on June 4, 1999, GPU Nuclear determined that a condition that |
| is outside the plant design basis may exist at TMI-1 due to potential |
| degraded performance of the Reactor Building [RB] Emergency Cooling System. |
| Measurements of indirect system performance parameters for the TMI-1 Reactor |
| Building Emergency Cooling System indicate that the air flow through the |
| system may be less than that assumed in the plant design basis. |
| |
| "Specifically, air flow in the RB Normal Cooling system, that utilizes duct |
| work and a flow damper common to both the RB Normal cooling system and the |
| RB Emergency Cooling System, has been found to be below previous air flow |
| measurements. The air flow reduction may be indicative of a reduced air flow |
| that would occur in the RB Emergency Cooling system if it was called upon to |
| function in the event of a design basis accident. The design basis flow for |
| the RB Emergency Cooling System is 25,000 CFM with the RB cooling fans in |
| slow speed. Engineering judgement is that the current flow rate may be below |
| 25,000 CFM if the system was called upon to function, hence the |
| identification of a condition outside the plant design basis. |
| |
| "Engineering judgement is that: the Reactor Building Emergency Cooling |
| System remains operable but may be degraded. The judgement that the system |
| is operable with degraded air flow is based on the difference between |
| conservative assumptions in environmental temperatures in the plant design |
| basis analysis and current environmental conditions and in view of the fact |
| that the environmental conditions within the Reactor Building in the design |
| basis accident should enhance the current potential degraded system air |
| flow. A formal internal justification of continued operation (JCO) will be |
| prepared to document the basis for the engineering judgement and will be |
| provided to the site NRC resident inspectors office. |
| |
| "Because GPU Nuclear has classified this condition as being potentially |
| outside the design basis of the plant, GPU Nuclear is notifying the NRC |
| Operations Center in accordance with 10 CFR 50.72(b)(1)(ii)(b). This |
| notification will be followed with a 30 day LER in accordance with 10 CFR |
| 50.73. |
| |
| "GPU Nuclear will document this condition in its 10 CFR 50 Appendix B |
| corrective action program and this potential non-conformance is being |
| addressed in accordance with the guidance provided in NRC Generic Letter |
| 91-18, Rev 1." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35799 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/04/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 19:05[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/04/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 07:25[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/04/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |DAVID HILLS R3 |
| DOCKET: 0707002 |WAYNE HODGES NMSS |
+------------------------------------------------+CHARLES MILLER IRO |
| NRC NOTIFIED BY: RICK LARSON | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 24 HOUR REPORT |
| |
| "ON 6/4/99 AT 0725 HRS. OPERATIONS PERSONNEL DISCOVERED THAT REQUIREMENT #5 |
| OF NUCLEAR CRITICALITY SAFETY ANALYSIS (NCSA) PLANT_003.A01 WAS NOT BEING |
| MET. THE REQUIREMENT, MONITORING SURGE DRUM PRESSURE ONCE EACH SHIFT WAS |
| BEING PERFORMED WITH THE INSTALLED PRESSURE INDICATOR WHICH WAS ISOLATED ON |
| 5/20/99 TO ALLOW MAINTENANCE TO CALIBRATE. WHEN THE INDICATOR COULD NOT BE |
| CALIBRATED IT WAS LEFT ISOLATED AND OPERATIONS WAS NOT MADE AWARE THAT OF |
| THIS CONDITION. SINCE THE LINE WAS VALVED OFF THE DRUM PRESSURE WAS NOT |
| MEASURED AS REQUIRED, THIS IS A LOSS OF A SINGLE CONTROL (CONCENTRATION) OF |
| THE DOUBLE CONTINGENCY PROGRAM. THE SECOND CONTROL (MODERATION) WAS |
| MAINTAINED THROUGHOUT THE EVENT. THE PRESSURE INDICATOR WAS VALVED IN AT |
| 0905 HRS. ON 6/4/99. PREVIOUS MAINTENANCE IN THE CASCADE REGARDING SURGE |
| DRUM CALIBRATION MAY HAVE RESULTED IN A SIMILAR SITUATION. |
| |
| "THE 'X' BANK SURGE DRUM WAS EVACUATED AND TAGGED OUT OF SERVICE FOR |
| MAINTENANCE. |
| THEREFORE, THE SURGE DRUM IS CONSIDERED EMPTY. ON 5/20/99 MAINTENANCE |
| VALVED OFF THE DRUM TO DO WORK ON THE PRESSURE SENSOR. THE DRUM REMAINED |
| VALVED OFF UNTIL 6/4/99. WHEN THE DRUM WAS VALVED BACK IN THE DRUM WAS |
| STILL EVACUATED. THIS INDICATED THAT THE NCSA PRESSURE LIMIT WAS NEVER |
| EXCEEDED (i.e., WET AIR IN-LEAKAGE DID NOT OCCUR), THEREFORE, THE SAFETY |
| SIGNIFICANCE OF THIS EVENT IS LOW AND A CRITICALITY WAS NOT POSSIBLE. |
| |
| "FOR CRITICALITY TO OCCUR THE SURGE DRUM WOULD HAVE TO HAVE MATERIAL IN IT |
| AND THE MATERIAL WOULD NAVE TO BE MODERATED BY WET AIR IN-LEAKAGE. THIS WAS |
| EXPECTED TO OCCUR IN THIS CASE BECAUSE THE DRUM WAS HOLDING ITS PRESSURE |
| BEFORE MAINTENANCE CALIBRATED THE PRESSURE SENSOR, AND THE FACT THAT OTHER |
| SURGE DRUMS IN THE SAME ROOM WERE OPERATING AND THE ROOM TEMPERATURE WAS |
| GREATER THAN 140�F. |
| |
| "THE ESTIMATED AMOUNT OF MATERIAL IN THE DRUM IS LESS THAN 600 gms. U-235 (A |
| SAFE MASS AT 10% ENRICHMENT) DUE TO THE FACT THAT THE DRUM WAS EVACUATED |
| PRIOR TO MAINTENANCE. WHEN THE PRESSURE SENSOR WAS VALVED BACK INTO THE |
| DRUM, THE DRUM WAS STILL AT A VACUUM (NOTE: THE NCSA PRESSURE LIMIT ON THE |
| DRUM IS 17 psia). THE MAXIMUM ENRICHMENT IN THIS DRUM IS 10%. THE FORM OF |
| THE MATERIAL IS EITHER UF6 OR UO2F2. |
| |
| "THE MAINTENANCE PROCEDURE REQUIRES THE PRESSURE INDICATOR TO BE ISOLATED |
| FOR CALIBRATION. THIS WAS DONE ON 5/20/99. WHEN THE SENSOR COULD NOT BE |
| CALIBRATED, THE LINE WAS LEFT VALVED OFF AND OPERATIONS DID NOT KNOW THIS. |
| THE NCSA REQUIRES THE PRESSURE ON THE DRUM TO BE MONITORED AND RECORDED EACH |
| SHIFT, OPERATIONS WAS READING THE MT&E SENSOR INSTALLED. HOWEVER, SINCE THE |
| LINE WAS VALVED OFF THE DRUM PRESSURE WAS NOT MEASURED AS REQUIRED. |
| |
| "THE RESIDENT NRC INSPECTOR HAS BEEN NOTIFIED." |
| |
| * * * UPDATE AT 2120 EDT ON 6/4/99 BY ERIC SPAETH TO FANGIE JONES * * * |
| |
| Clarification: the normal pressure indicator is read in the control room. |
| That indicator is still not calibrated and a local calibrated pressure gauge |
| was valved in for indication on 6/4/99 and is read locally each shift. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35800 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 06/05/1999|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 01:27[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 06/04/1999|
+------------------------------------------------+EVENT TIME: 23:55[EDT]|
| NRC NOTIFIED BY: WILLIAM KISNER |LAST UPDATE DATE: 06/05/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KENNETH BARR R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 85 Power Operation |85 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LIVE TURTLE FOUND IN INTAKE STRUCTURE |
| |
| The licensee notified the Florida Department of Environmental Protection |
| regarding the discovery of a live Loggerhead Turtle on the intake bar racks. |
| The turtle was removed and transported to the mariculture center. The NRC |
| resident inspector has been informed of this notification by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35801 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 06/06/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 18:07[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 06/06/1999|
+------------------------------------------------+EVENT TIME: 14:40[CDT]|
| NRC NOTIFIED BY: MIKE MacLENNON |LAST UPDATE DATE: 06/06/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID HILLS R3 |
|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 |55 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LIGHTNING STRIKE CAUSED SOME MINOR ALARMS AND PARTIAL GROUP ONE ISOLATIONS |
| |
| "On 6/6/99 at approximately 1440 hours, a lightning strike caused valves |
| 1-0220-44 and 1-0220-45, Reactor Recirculation sample valves, to close on an |
| invalid signal. These valves close automatically on a Group One isolation, |
| and therefore this is considered to be an ESF actuation. |
| |
| "The power change indicated above was also a result of the lightning strike. |
| An emergency load reduction was made in response to a partial loss of |
| feedwater heaters. Reactor recirculation flow was manually reduced and |
| control rods were inserted to reduce the flow control line below 100%. |
| Miscellaneous other minor alarms were received on both units due to the |
| lightning strike. |
| |
| "The above mentioned sample valves have been reopened, and a load increase |
| to full power has been initiated as of 1635 hours." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35802 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 06/06/1999|
| UNIT: [] [2] [] STATE: FL |NOTIFICATION TIME: 21:14[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 06/06/1999|
+------------------------------------------------+EVENT TIME: 18:45[EDT]|
| NRC NOTIFIED BY: ALAN HALL |LAST UPDATE DATE: 06/06/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |KENNETH BARR R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A N 0 Hot Standby |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| WITH THE REACTOR SHUTDOWN, AN AUTOMATIC REACTOR TRIP WAS GENERATED |
| |
| "At 1845 EDT, an inadvertent partial opening of the 2B MSIV occurred, |
| causing a steam generator pressure transient that resulted in an Reactor |
| Protection System Asymmetrical Steam Generator Pressure Transient. The |
| plant was in Mode 3, all control element assemblies were fully inserted, the |
| trip circuit breakers were closed, and opened as expected in response to the |
| trip signal. Investigation proceeding." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
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