Event Notification Report for April 26, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/23/1999 - 04/26/1999
** EVENT NUMBERS **
35600 35612 35622 35623 35624 35625 35627 35628 35629 35630 35631
35632
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35600 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/17/1999|
| UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 11:58[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/17/1999|
+------------------------------------------------+EVENT TIME: 09:59[CDT]|
| NRC NOTIFIED BY: DAVE SLAGER |LAST UPDATE DATE: 04/23/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN JACOBSON R3 |
|10 CFR SECTION: | |
|ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N Y 99 Power Operation |99 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FAILURE OF A PRIMARY CONTAINMENT AIR SAMPLE RETURN ISOLATION VALVE TO MEET |
| MAXIMUM INSERVICE TEST STROKE-TIME REQUIREMENTS |
| |
| While performing quarterly valve stroke-time testing on Unit 3, a primary |
| containment air sample return isolation valve exceeded its specified maximum |
| stroke-time limit. The sample return line was isolated in accordance with |
| Technical Specification 3.7.D for primary containment isolation valves, and |
| this action satisfied the 4-hour limiting condition for operation action |
| statement requirements. The second in-line primary containment isolation |
| system valve remains operable. |
| |
| The licensee stated that no other valves failed to meet the maximum |
| stroke-time limits. The licensee also stated that, during a test that was |
| performed last month, the valve in question was identified as being in the |
| 'Alert' time range for inservice test timing requirements and that it was |
| being tested per the required increased testing frequency. Corrective |
| actions are being initiated, and troubleshooting activities are in |
| progress. |
| |
| The licensee plans to notify the NRC resident inspector. |
| |
| *** UPDATE ON 04/23/99 AT 0443 FROM GADBOIS TO GOULD *** RETRACTION |
| |
| UPON FURTHER REVIEW, IT WAS DETERMINED THAT THIS EVENT DID NOT CONSTITUTE A |
| REPORTABLE CONDITION SINCE THE PENETRATION HAD AN OPERABLE REDUNDANT VALVE |
| WHICH COULD HAVE ISOLATED THE CONTAINMENT PENETRATION. THEREFORE, THE |
| LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. |
| |
| THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE R3DO (LEACH) |
| WAS NOTIFIED BY THE NRC OPERATIONS OFFICER. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35612 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: MA DEPT OF PUBLIC HEALTH RCP |NOTIFICATION DATE: 04/21/1999|
|LICENSEE: AEA TECHNOLOGIES QSA, INC |NOTIFICATION TIME: 15:00[EDT]|
| CITY: BURLINGTON REGION: 1 |EVENT DATE: 04/21/1999|
| COUNTY: STATE: MA |EVENT TIME: 14:00[EDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 04/23/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MOHAMED SHANBAKY R1 |
| |FREDERICK COMBS NMSS |
+------------------------------------------------+JOSEPH GIITTER IRO |
| NRC NOTIFIED BY: KEN TRAEGDE |DONNA MARIE PEREZ IP |
| HQ OPS OFFICER: DICK JOLLIFFE |LEN WERT R2 |
+------------------------------------------------+DALE POWERS R4 |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
|NOCM COMM ASST BRIEF | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - SHIPMENT OF 8 Ir-192 SOURCES (866 CURIES TOTAL) FROM BURLINGTON, MA, |
| OVERDUE IN MEXICO - |
| |
| AT 1500 EDT ON 04/21/99, KEN TRAEGDE OF THE MA DEPARTMENT OF PUBLIC HEALTH |
| RADIATION CONTROL PROGRAM (RCP) LOCATED IN BOSTON, MA, REPORTED THAT ON |
| 04/16/99, AEA TECHNOLOGY QSA, INC., LOCATED IN BURLINGTON, MA, SHIPPED A |
| MODEL #855 SOURCE CHANGER LOADED WITH 8 Ir-192 SOURCES (TOTALING 866 CURIES) |
| VIA FEDERAL EXPRESS TO VICONT S.A. DE C.V. LOCATED IN TOLUCA, MEXICO. THE |
| UNDAMAGED PACKAGE HAD A TRANSPORT INDEX OF 1.4 (NORMAL READINGS OF 1.4 mR/HR |
| AT 1 METER AND 55 mR/HR AT THE SURFACE) AT THE TIME OF SHIPMENT. |
| |
| THE SHIPMENT WAS SCHEDULED TO ARRIVE IN MEXICO ON 04/17/99. AS OF 1400 EDT |
| ON 04/21/99, THE RECIPIENT (VICONT S.A. DE C.V.) HAD RECEIVED THE SHIPPING |
| PAPERS BUT NOT THE CONTAINER. THE SHIPPER AND FEDERAL EXPRESS HAVE LAUNCHED |
| A FULL SEARCH FOR THE PACKAGE. THE FEDERAL EXPRESS HAZARDS MATERIAL |
| INVESTIGATION TEAM HAS CONDUCTED A PHYSICAL SEARCH OF EXPRESS DEPOTS IN |
| BOSTON, MEMPHIS, LOS ANGELES, AND MEXICO. |
| |
| THE LICENSE NUMBERS ARE: SU-1485, 12-8361, 52-0243, 54-0237, AND 58-0242. |
| |
| THE NRC OPERATIONS OFFICER NOTIFIED THE DOT NATIONAL RESPONSE CENTER |
| (GAUTHIER); REPORT NUMBER 481132. |
| |
| (CONTACT THE NRC OPERATIONS OFFICER FOR APPLICABLE TELEPHONE NUMBERS.) |
| |
| *********************************** UPDATE AT 1345 ON 04/22/99 BY JONES |
| *********************************** |
| |
| The NRC entered the Monitoring Phase of Normal Mode at 1345 on 04/22/99. |
| The NRC operations officer notified, the R1DO (Shanbaky), Region 1 (Miller), |
| IRO (Congel and Giitter), NMSS (Paperiello), RCT (Weinstein), PAO (Gagner), |
| EDO's office (Charleen Raddatz), and Chairman's office (Holian). The RCT |
| notified FEMA (Dan Rishe), DOE (Thomas Yates), EPA (Ms. Reddy), USDA (Bob |
| Conley), HHS/CDC (James Raab), and DOT (Rick Boyle). |
| |
| *********************************** UPDATE AT 1600 ON 04/22/99 BY JONES |
| *********************************** |
| |
| A Commissioner's Assistants Briefing was conducted at 1600 on 04/22/99. The |
| following notifications were made (* office did not participate): IRO (Joe |
| Giitter and Eric Weinstein), Chairman Jackson (Dan Gillen), Commissioner |
| Dicus (Joel Lubenau), Commissioner Diaz (Patrick Castleman), Commissioner |
| McGaffigan (Janet Schlueter), Commissioner Merrifield (JohnThoma), EDO (*), |
| DEDE (*), NMSS (Don Cool and Carl Paperiello), NMSS EO (Fred Combs), R1DO |
| (Mohamed Shanbaky), PAO (Joe Gilland), CAO (Thomas Madden), SECY (Andrew |
| Bates), SP (Paul Lohaus), IP (Ron Hauber), Region 1 (Felicia Hinson and Jim |
| Wiggins, etc), and Region 2 (Doug Collins, Chuck Hosey, and Dick Woodruff). |
| The briefer was Fred Combs of NMSS. |
| |
| At 1610, the NRC operations officer played a tape of briefing for EDO (Dan |
| Martin) and DEDE (Jocelyn Mitchell). |
| |
| ****************************** UPDATE AT 1230 ON 04/23/99 BY TROCINE AND |
| JONES ****************************** |
| |
| A conference call was conducted at 1230 on 04/23/99 to update the status of |
| this event. The following NRC offices participated (among others): IRO |
| (Himes), NMSS (Brach, Combs, and Cook), Region 1 (Loyd), Region 2 (Collins |
| and Woodruff), Region 4 (Andrews), PAO (Hayden), IP (Lieberman), SP |
| (Lohaus), and EDO (Raddatz). In addition, the following agencies |
| participated: Department of Transportation (Rick Boyle), Massachusetts |
| Department of Public Health RCP (Ken Traegdy), Federal Express (Scott Mugno, |
| Pat Oppenheimer, and Roy Parker), State of Tennessee (Alan Grewe), Tennessee |
| Division of Radiation Health (Eddy Nanney), AEA Technologies QSA, Inc. (Eric |
| Okvist), and Environmental Protection Agency located in Atlanta (Paul |
| Wagner). |
| |
| During this conference call, representatives of Federal Express reported |
| that they are confident that the shipment of 8 Ir-192 sources left Boston. |
| They issued an 'all-points' search order, faxed a description to all |
| 'logical' locations, and conducted repeat physical searches in Memphis, |
| Boston, and Mexico, all without locating the shipment to date. (The Los |
| Angeles depot was not searched as had been reported on 04/21/99.) |
| Massachusetts and Tennessee health authorities conducted radiological |
| surveys in Boston and Memphis on 04/22/99 with negative results. |
| |
| Rick Boyle of the Department of Transportation notified the competent |
| authority in Mexico, and Federal Express requested a detailed search of the |
| Customs facilities in Mexico City. |
| |
| The next conference call is scheduled for 1230 EDT on Wednesday, 04/28/99. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35622 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 04/23/1999|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 04:33[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 04/23/1999|
+------------------------------------------------+EVENT TIME: 02:14[CDT]|
| NRC NOTIFIED BY: WELLER |LAST UPDATE DATE: 04/23/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MELVYN LEACH 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 N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HPCI SYSTEM DECLARED INOPERABLE, AND PLANT ENTERED LCO ACTION STATEMENT. |
| |
| THE HPCI SYSTEM WAS DECLARED INOPERABLE FROM 0214 CDT TO 0220 CDT DUE TO |
| MOISTURE IN THE TURBINE STEAM INLET LINE. A 14-DAY LCO ACTION STATEMENT WAS |
| ENTERED, AND RCIC WAS VERIFIED OPERABLE. HPCI TURBINE INLET HIGH DRAIN POT |
| LEVEL ANNUNCIATION WAS RECEIVED DUE TO STROKING MO-2036 (TURBINE STEAM |
| SUPPLY VALVE) AS PART OF THE REACTOR SHUTDOWN PROCEDURE AT REACTOR PRESSURE |
| OF 500 PSIG. THE STEAM LINE MANUAL DRAIN VALVE WAS OPENED, AND THE |
| ANNUNCIATOR CLEARED AT 0220 CDT. HPCI WAS DECLARED OPERABLE AND IN STANDBY. |
| THE 14-DAY LCO ACTION STATEMENT WAS ALSO EXITED AT 0220 CDT. |
| |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35623 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 04/23/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 10:16[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 04/23/1999|
+------------------------------------------------+EVENT TIME: 07:53[EDT]|
| NRC NOTIFIED BY: GILLOW |LAST UPDATE DATE: 04/23/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 |
|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 35 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE PLANT HAD A REACTOR TRIP FROM 35% POWER ON A 2-OUT-OF-4 POWER RANGE HIGH |
| SIGNAL. |
| |
| THE REACTOR TRIP OCCURRED WHILE THE PLANT WAS COMING OUT OF A REFUELING |
| OUTAGE AND THE I&C TECHNICIANS WERE WORKING ON THE NUCLEAR INSTRUMENTATION |
| RACKS ADJUSTING POWER RANGE TRIP SETPOINTS. CHANNEL 1 HAD JUST BEEN |
| COMPLETED, AND CHANNEL 2 WAS IN PROGRESS WITH BOTH BISTABLES TRIPPED IN THE |
| CHANNEL 2 PROTECTION RACKS. AT THIS POINT, CONTROL ROOM TURNOVER HAD |
| STARTED, AND THE TECHNICIANS HAD STOPPED WORK UNTIL TURNOVER WAS COMPLETE. |
| UPON RESUMING WORK, THE TECHNICIANS INADVERTENTLY WENT TO NIS CHANNEL 3 AND |
| PULLED INSTRUMENT POWER FUSES. THE REACTOR TRIPPED ON 2 OUT OF 4 POWER |
| RANGE HI LEVEL IMMEDIATELY UPON PULLING THE CHANNEL 3 FUSES. ALL RODS FULLY |
| INSERTED, NO ECCS OCCURRED, AND NO SAFETY RELIEF VALVES LIFTED. THE PLANT |
| IS USING THE ATMOSPHERIC RELIEF VALVES AS THE HEAT SINK. THE PLANT IS |
| CURRENTLY IN MODE 3, Tavg IS 547�F, AND RCS PRESSURE AT 2,235 PSIG. |
| |
| SINCE THE LICENSEE WAS COMING OUT OF A REFUELING OUTAGE, THE MAIN STEAM |
| ISOLATION VALVES WERE CLOSED DUE TO LOW DECAY HEAT, AND THE MAIN STEAM |
| GENERATOR ATMOSPHERIC VALVE ON EACH STEAM GENERATOR WAS USED TO MAINTAIN |
| Tavg. |
| |
| THE INCIDENT WAS DUE TO PERSONNEL ERROR. |
| |
| THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 35624 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NATIONAL INSTITUTE OF HEALTH |NOTIFICATION DATE: 04/23/1999|
|LICENSEE: NATIONAL INSTITUTE OF HEALTH |NOTIFICATION TIME: 13:38[EDT]|
| CITY: BETHERSDA REGION: 1 |EVENT DATE: 04/21/1999|
| COUNTY: MONTGOMERY STATE: MD |EVENT TIME: 14:30[EDT]|
|LICENSE#: 19-00296-17 AGREEMENT: Y |LAST UPDATE DATE: 04/23/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MOHAMED SHANBAKY R1 |
| |FREDERICK COMBS NMSS |
+------------------------------------------------+JOSEPH GIITTER IRO |
| NRC NOTIFIED BY: ROBERT ZOON | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AN IRRADIATOR FAILED TO PROPERLY RETURN THE SOURCE TO THE FULLY SHIELDED |
| POSITION. |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "This is a report in accordance with condition 17.E. of license 19-00296-17 |
| which requires that with respect to each J. L. Shepherd and Associates Mark |
| 1 Cesium-137 Irradiator, we ' ... notify the Commission by telephone ... if |
| ... any malfunction of the irradiator is detected. |
| |
| "At approximately 2:30 p.m. April 21, 1999, a health physicist (HP) in the |
| Radiation Safety Branch was continuing a quarterly inspection and leak test |
| procedure which he had initiated on April 19, 1999. During this follow-up |
| visit, he became aware of an apparent problem with a J. L. Shepherd Mark I |
| Cesium-137 irradiator, which is located in Building 37, Room B440. This |
| self-contained self-shielded irradiator contains approximately 3,850 Ci of |
| Cs-137. |
| |
| "The [HP] reported the results of his investigation to me at 9:15 a.m. this |
| morning. The problem was reported to the HP on April 21 by a designated |
| user who explained that the source failed on at least one occasion to return |
| to the fully shielded position following an irradiation procedure. The door |
| interlock functioned as designed, which prevented the door from being |
| opened. Thus, this situation resulted in NO safety problem or radiation |
| exposure. |
| |
| "The HP, continuing his investigation, was able to duplicate a similar |
| problem one additional time during the inspection. However, numerous |
| repeated attempts to duplicate the problem did not result in a failure of |
| the irradiator to properly stow the source. The HP did not, therefore, |
| judge the irradiator to have malfunctioned. |
| |
| "Following the HP's discussion with me this morning, it was my judgement |
| that the problem observed could be interpreted as a malfunction of the |
| irradiator. Therefore, effective this morning, I directed the irradiator |
| custodian to remove this irradiator from service and to contact J. L. |
| Shepherd for maintenance to correct this problem. At that time, I also |
| elected to report this apparent malfunction directly to you [Judith Joustra, |
| Chief, Nuclear Materials Safety Branch, Region 1]. Upon your advice, I am |
| simultaneously reporting this finding to the NRC Operations Center. |
| |
| "Upon receipt of the report of maintenance from the J. L. Shepherd service |
| representative, I will forward you the explanation for the irradiator's |
| failure to operate." |
| |
| (Call the NRC operations officer for a site contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35625 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 04/23/1999|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 16:42[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/23/1999|
+------------------------------------------------+EVENT TIME: 16:00[EDT]|
| NRC NOTIFIED BY: S. SAUER |LAST UPDATE DATE: 04/23/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY 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
+------------------------------------------------------------------------------+
| AUXILIARY BUILDING DISCOVERED AT POSITIVE PRESSURE TO THE OUTSIDE. |
| |
| The licensee determined at 1600 on 04/23/99 that this report met the |
| criteria for reporting under 10CFR50.72 as a 1-hour report. |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On 04/13/99 at 2135, the Unit 1 auxiliary building was found to be at a |
| +0.03 inches of water with respect to the outdoors. The Updated Final |
| Safety Analysis Report (UFSAR) states that the auxiliary building is |
| designed to be at a slight negative pressure continuously with respect to |
| the outdoors, to satisfy the criterion for preventing the uncontrolled |
| release of radioactivity. Subsequent investigation found that the #12 |
| auxiliary building exhaust fan was rotating backwards. The fan had been |
| returned to service at 1337 on 04/13/99, the fan was removed from service at |
| 2216. Maintenance inspections had been performed earlier that day that |
| required the motor leads to be disconnected. The apparent cause is miss |
| wiring of the motor by the maintenance technician. The fan was reworked and |
| returned to service at 1110 on 04/14/99. Tech Spec 3.7.7.1 was in effect |
| for the duration." |
| |
| The licensee intends to notify the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35627 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/24/1999|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 05:09[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/24/1999|
+------------------------------------------------+EVENT TIME: 04:19[EDT]|
| NRC NOTIFIED BY: BRIAN WEAVER |LAST UPDATE DATE: 04/24/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: |WILLIAM BATEMAN NRR |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |JOSEPH GIITTER IRO |
|ACCS 50.72(b)(1)(iv) ECCS INJECTION | |
|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 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR SCRAM DUE TO UNKNOWN ELECTRICAL TRANSIENT |
| |
| The reactor scrammed due to an unknown electrical transient. All control |
| rods fully inserted into the core. Both electric-driven reactor feedwater |
| pumps tripped, all three condensate booster pumps tripped, and the |
| recirculation pumps tripped. The plant is in natural circulation with high |
| pressure core spray (HPCS) system injecting and maintaining reactor vessel |
| water level between 160 to 200 inches. (Normal reactor vessel water level |
| is 184 inches, and the top of the active fuel is -18 inches.) Reactor core |
| isolation cooling (RCIC) and HPCS received automatic initiation signals on |
| Level 2, and the Division 3 diesel automatically started but did not load. |
| The RCIC pump failed to come up to speed and has been tripped. The main |
| steam isolation valves are open, and reactor vessel pressure is being |
| maintained at 600 to 700 psig. Uninterruptible power supply (UPS) "3B" |
| tripped and has a blown fuse which prevents resetting of the inboard |
| containment isolation valves. Both Containment Monitoring System(CMS) |
| cabinets 10A and 10B are isolated (leak detection for particulate and |
| gaseous) causing entry into Technical Specification 3.0.3. Due to UPS "3B" |
| being tripped, the licensee has a one-half isolation signal to the main |
| steam isolation valves. UPS "3B" provides logic to the scram system, etc. |
| (UPS "3B" is essentially a major logic power supply for UPS.) |
| |
| The electrical transient (not sure if the transient was caused from offsite |
| site power loss) caused a partial loss of lighting in the control room, a |
| complete loss of lighting to the turbine building (was reported), and a loss |
| of site perimeter lighting for a very short period of time. All UPS went to |
| a battery source of power for a short period of time and then transferred |
| back to normal power source (normally happens on a big electrical |
| transient). All electrical in-house buses powered up, and the plant is |
| stable. A condensate booster pump has been reestablished, and the licensee |
| is starting to investigate what caused the electrical transient, RCIC not |
| coming up to speed (places them in Tech Spec 3.7.4), and what caused the |
| fuse to blow to UPS "3B." |
| |
| The licensee had not, at the time of this call, checked with Unit 1 to see |
| if it had experienced a power loss for a short period of time. |
| |
| The NRC resident inspector will be notified of this event by the licensee. |
| |
| ***UPDATE AT 0751 EDT FROM ROY GREEN TAKEN BY MACKINNON*** |
| |
| The licensee updated this event to add the 4-hour notifications under 10 CFR |
| 50.72 (b)(2) for a reactor protection system actuation, engineered safety |
| feature (ESF) actuations, and accident mitigation. The 4-hour notifications |
| were required for the reactor scram and the following ESF actuations: |
| reactor water cleanup system isolation, standby gas initiation, control room |
| special filter train initiation, reactor vessel water Level 2 containment |
| isolations, and Division 3 (HPCS) automatic start on HPCS initiation. The |
| third 4-hour notification was required for accident mitigation due to single |
| train RCIC failure upon initiation. |
| |
| Plant Status: |
| |
| The scram has been reset, normal cooldown is in progress via the turbine |
| bypass valves, reactor vessel water level is being maintained in its normal |
| band with normal feedwater system, and UPS-3B remains de-energized |
| preventing containment isolation recovery. Troubleshooting is in progress |
| on UPS-3B and RCIC. (The region of instability on the power to flow map was |
| not entered.) |
| |
| The licensee plans to place the unit in a Cold Shutdown condition on natural |
| circulation. |
| |
| The NRC resident inspector was notified of this update by the licensee. The |
| R1DO ( Mohamed Shanbaky) was notified by the NRC operations officer. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35628 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: GAMMA-METRICS |NOTIFICATION DATE: 04/23/1999|
|LICENSEE: GAMMA-METRICS |NOTIFICATION TIME: 18:00[EDT]|
| CITY: SAN DIEGO REGION: 4 |EVENT DATE: 04/23/1999|
| COUNTY: STATE: CA |EVENT TIME: [PDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 04/24/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MOHAMED SHANBAKY R1 |
| |LEN WERT R2 |
+------------------------------------------------+MELVYN LEACH R3 |
| NRC NOTIFIED BY: ROBERT BARNES |VERN HODGE(FAX) NRR |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INFORMATION ON A DEVIATION THAT DOES NOT REACH THE LEVEL OF A PART 21 |
| REPORT |
| |
| There was an incorrect resistor shipped on log amplifier printed circuit |
| assemblies. The worst case environmental temperature deviation would cause |
| a maximum deviation of 6% (equivalent full-scale) error in the indicating |
| region from 3 X 10-3% to 50% power. This would not compromise the ability |
| to monitor safe shutdown reactor power level adequately during and after a |
| design basis event. |
| |
| The following text is a portion of a facsimile received from GAMMA-METRICS: |
| |
| "Our lot control capability allowed us to determine that nineteen of the |
| incorrect resistors were shipped from GAMMA-METRICS to our customers. ... We |
| are recalling all nineteen defective resistors or the printed circuit |
| assemblies. We will replace the resistors with the correct component and |
| re-certify the repair at no charge to any of the listed customers." |
| |
| The following is a list of the facilities affected: |
| |
| 1. Georgia Power, Vogtle 1 and 2 - 9 assemblies (replaced in March 1999) |
| 2. Duke Energy, Catawba - 1 assembly |
| 3. AEP DC Cook - 2 assemblies (not installed) |
| 4. Ontario Hydro, Pickering - 1 assembly (not installed) |
| 5. Maine Yankee - 4 assemblies (not installed and plant shutdown for |
| decommissioning) |
| 6. Penn State University - 2 assemblies (not installed) |
| |
| There were letters sent to the affected customers. |
| |
| (Call the NRC operations officer for a contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35629 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 04/24/1999|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 13:09[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 04/24/1999|
+------------------------------------------------+EVENT TIME: [CDT]|
| NRC NOTIFIED BY: KEVIN PETERSON |LAST UPDATE DATE: 04/24/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MELVYN LEACH 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 N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR WATER LEVEL HIGH ENOUGH TO ENTER THE MAIN STEAM LINES (Refer to |
| event numbers 35617 and 35618 for event-related information.) |
| |
| During an engineering evaluation of the reactor scram that occurred on |
| 04/22/99, it was determined that reactor water level entered the main steam |
| lines. This potentially made reactor core isolation cooling and high |
| pressure coolant injection inoperable. The cause of the high water level |
| condition is under investigation. |
| |
| The licensee notified the NRC Resident Inspector and intends to notify state |
| and local government agencies. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35630 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 04/24/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 15:28[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 04/24/1999|
+------------------------------------------------+EVENT TIME: [CDT]|
| NRC NOTIFIED BY: JIM SCHOTTEL |LAST UPDATE DATE: 04/24/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MELVYN LEACH R3 |
|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 N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) OUT OF SERVICE DUE TO MAINTENANCE. |
| |
| Planned maintenance on an uninterruptible power supply bus (1B) for the |
| process computer will disable some points on the SPDS for 48 hours. |
| Operators are taking compensatory measures for monitoring parameters. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35631 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/24/1999|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 22:15[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/24/1999|
+------------------------------------------------+EVENT TIME: 19:36[CDT]|
| NRC NOTIFIED BY: MARK ANDREWS |LAST UPDATE DATE: 04/24/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MELVYN LEACH 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH STEAM GENERATOR LEVEL ESF ACTUATION |
| |
| During cooldown, after performing a plant shutdown for a refueling outage, |
| narrow range level was noted to be increasing in the '2A' and '2C' steam |
| generators. The feedwater isolation valves were checked closed, and |
| additional manual isolation valves were closed. Steam generator blowdown |
| was in the process of being put in service when level reached the P14 |
| setpoint which caused an engineered safety features actuation (includes main |
| feedwater pump trip and feedwater isolation signal). |
| |
| Further investigation found auxiliary feedwater valves open that together |
| with the pressure head from the water level in the condensate tank was |
| sufficient to feed the steam generators. |
| |
| Steam generator level was restored once blowdown was established. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35632 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 04/26/1999|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 01:41[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/26/1999|
+------------------------------------------------+EVENT TIME: 00:01[EDT]|
| NRC NOTIFIED BY: FERNSLER |LAST UPDATE DATE: 04/26/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MOHAMED SHANBAKY R1 |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 2 Startup |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNIT 2 WAS MANUALLY SCRAMMED FROM 2% POWER TO PERMIT ENTRY INTO THE DRYWELL |
| FOR REPAIR WORK. |
| |
| THE UNIT WAS MANUALLY SHUTDOWN TO PERMIT ENTRY INTO CONTAINMENT TO PERFORM |
| REPAIRS TO THE TRANSVERSING INCORE PROBE(TIP) CHANNEL TUBING. PRIOR TO |
| SHUTDOWN THE UNIT WAS IN THE PROCESS OF RESTARTING FOLLOWING THE 9TH |
| REFUELING OUTAGE. DURING POST MAINTENANCE TESTING, A RESTRICTION WAS |
| DISCOVERED IN THE TUBING OF THE "C" TIP MECHANISM. THIS PREVENTED INSERTION |
| OF ITS DETECTOR AND CALIBRATION OF ITS ASSOCIATED LPRM. IN ORDER TO PERFORM |
| REPAIRS, THE REACTOR HAD TO BE SHUTDOWN FOR DRYWELL ENTRY. FOLLOWING |
| SHUTDOWN REACTOR WATER LEVEL REMAINED ESSENTIALLY UNCHANGED AT 35.7" AS |
| RECORDED ON THE NARROW RANGE INSTRUMENTATION. ALL RODS FULLY INSERTED, NO |
| ECCS INITIATIONS OR DIESEL STARTS OCCURRED AND NO SAFETY RELIEF VALVES |
| LIFTED. THIS EVENT IS NOT REPORTABLE AS A RPS ACTUATION SINCE IT IS |
| PROCEDURALLY RECOGNIZED AS PRE-PLANNED. HEAT SINK IS THE SHUTDOWN COOLING |
| TO THE SUPPRESSION POOL. THEY WILL CONTINUE COOLDOWN TO MODE 4. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021