Event Notification Report for July 26, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/23/1999 - 07/26/1999
** EVENT NUMBERS **
31161 35867 35897 35948 35949 35950 35951 35952 35953 35954 35955 35956
35957 35958
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 31161 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CAP ENGINEERING CONSULTANTS |NOTIFICATION DATE: 10/16/1996|
|LICENSEE: CAP ENGINEERING CONSULTANTS |NOTIFICATION TIME: 15:14[EDT]|
| CITY: CORAL GABLES REGION: 2 |EVENT DATE: 10/15/1996|
| COUNTY: POLK STATE: FL |EVENT TIME: 00:00[EDT]|
|LICENSE#: FL-2611-1 AGREEMENT: Y |LAST UPDATE DATE: 07/23/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CAUDLE JULIAN RDO |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: REGION 2 (WOODRUFF) | |
| HQ OPS OFFICER: RUDY KARSCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CAP ENGINEERING CONSULTANTS, CORAL GABLES, FL. |
| |
| A TROXLER MODEL 3440 MOISTURE DENSITY GAGE WAS STOLEN FROM THE BACK OF A |
| PICKUP TRUCK. THE GAGE CONTAINED 9 mCi OF CESIUM-137 AND 44 mCi OF Am-Be. |
| THE LICENSEE HOLDS A FLORIDA LICENSE AND REPORTED THE INCIDENT TO FLORIDA ON |
| 10/15/96. REGION 2 (WOODRUFF) REPORTED THE EVENT TO THE OPERATIONS CENTER. |
| REGION 2 IS ISSUING PN-072. |
| |
| * * * UPDATE AT 1405 ON 07/23/99 FROM EAKINS TO CHAUNCEY GOULD * * * |
| |
| THE STATE OF FLORIDA BUREAU OF RADIATION CONTROL WAS INFORMED ON 07/23/99 |
| THAT THE STOLEN TROXLER MOISTURE DENSITY GAGE HAD BEEN RECOVERED IN WEBSTER, |
| FL. SEE EVENT #35949 FOR ADDITIONAL DETAILS. THE NRC OPERATIONS OFFICER |
| NOTIFIED R2DO (ED McALPINE) AND NMSS EO (DON COOL). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|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: 07/23/1999|
| 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
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM 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 the HPCI System 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. |
| |
| * * * UPDATE AT 1449 EDT ON 07/23/99 FROM STANLEY GAMBLE TO S. SANDIN * * * |
| |
| The licensee is retracting this report based on the following: |
| |
| The HPCI System was conservatively declared inoperable due to the potential |
| for water to be present in the turbine as a result of a plugged flow orifice |
| on the turbine exhaust drain pot drain line. The plugged orifice was |
| discovered during performance of a test specifically designed to ensure that |
| exhaust drain pot drain line flow path is operable. Testing is routinely |
| scheduled the day following normal HPCI System surveillance testing since |
| operation of the HPCI System is the initiator for plugging of the flow |
| orifice. |
| |
| The basis for this retraction is that a minimal amount, less than one |
| gallon, of condensate was drained from the exhaust drain pot when the flow |
| orifice piping was disassembled. The amount of condensate was much less |
| than the amount required to adversely impact HPCI System operability. It |
| would require in excess of 40 gallons of condensate to fill the exhaust |
| drain pot to a level that would result in condensate entering the turbine or |
| exhaust line. Therefore, the HPCI System was operable and capable of |
| performing its safety function until it was removed from service to clear |
| the flow orifice. |
| |
| The licensee informed the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified R1DO (Jim Noggle). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35897 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 07/06/1999|
| UNIT: [] [2] [] STATE: VA |NOTIFICATION TIME: 02:44[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/06/1999|
+------------------------------------------------+EVENT TIME: 02:04[EDT]|
| NRC NOTIFIED BY: LISA HILBERT-SEMMES |LAST UPDATE DATE: 07/23/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PAUL FREDRICKSON R2 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Hot Shutdown |0 Intermediate Shut|
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MODE CHANGE INITIATED AS PART OF A TECHNICAL SPECIFICATION REQUIRED |
| SHUTDOWN |
| |
| "At 1810 hours on 7-5-99, with Surry Power Station Unit 2 at Hot Shutdown |
| (HSD) following a reactor trip, the 'A' Cold Leg Loop Stop Valve (Mark |
| number 2-RC-MOV-2591) was removed from it's backseat in accordance with |
| station procedure 2-GOP-2.4. Upon reopening the valve, full open indication |
| was not received. In accordance with Technical Specification 3.17.1 and |
| 3.0.1, a 30 hour clock to Cold Shutdown (CSD) LCO was started. The valve |
| was de-energized by opening it's breaker. A cooldown to CSD was initiated |
| at 2050 on 7-5-99. At 0204 on 7-6-99, a review of Station procedures and |
| 10CFR50.72 determined that a one hour report was required for commencing the |
| RCS cooldown in accordance with the Technical Specification LCO. |
| |
| "There were no radiation releases due to this event, nor were there any |
| personnel injuries or contamination events. |
| |
| "Unit 2 is currently in Intermediate Shutdown with RCS cooldown in progress |
| in accordance with station procedures. |
| |
| "Unit 1 was not affected by this event and remains stable at 100% power and |
| 824 MWe. |
| |
| "This event is being reported in accordance with 10CFR50.72(b)(1)(i)(A)." |
| |
| The Licensee informed the NRC Resident Inspector. |
| |
| * * * UPDATE AT 0940 ON 07/23/99 FROM RAWLEIGH DILLARD TO JOLLIFFE * * * |
| |
| A review of NUREG 1022 with respect to 10CFR50.72(b)(1)(i)(A) provides the |
| following clarification: "the phrase 'initiation of any nuclear plant |
| shutdown' includes action to start reducing reactor power, i.e., adding |
| negative reactivity to achieve a nuclear plant shutdown required by |
| Technical Specifications. The 'initiation of any nuclear plant shutdown' |
| does not include mode changes required by Technical Specifications if |
| initiated after the plant is already in a shutdown condition." |
| |
| Unit 2 achieved Hot Shutdown Mode at 1122 on 07/05/99 after a reactor trip. |
| Based on the information given above in NUREG 1022, a one hour report was |
| not required for commencing the cooldown to Cold Shutdown Mode as this was a |
| mode change after Unit 2 was already in a shutdown condition. The actions |
| taken by the Licensee were prudent and represented a conservative decision |
| by the Licensee. |
| |
| Thus, the Licensee desires to retract the above report based on the above |
| discussion. |
| |
| The Licensee informed the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R2DO Ed McAlpine. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35948 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: OR DEPT OF HEALTH RAD PROTECTION |NOTIFICATION DATE: 07/23/1999|
|LICENSEE: EUGENE SAND AND GRAVEL COMPANY |NOTIFICATION TIME: 12:06[EDT]|
| CITY: EUGENE REGION: 4 |EVENT DATE: 07/22/1999|
| COUNTY: STATE: OR |EVENT TIME: 16:26[PDT]|
|LICENSE#: ORE-90643 AGREEMENT: Y |LAST UPDATE DATE: 07/23/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ELMO COLLINS R4 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: WRIGHT | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TROXLER MOISTURE DENSITY GAUGE DAMAGED AT A FLORENCE, OR. JOBSITE |
| |
| A TROXLER MOISTURE DENSITY GAUGE SERIES 3400 CONTAINING 9 MILLICURIES OF |
| CESIUM-137 AND 44 MILLICURIES OF AMERICIUM-241-BERYLLIUM WAS RUN OVER BY A |
| PICKUP TRUCK. THE SOURCE ROD WAS IN THE STORAGE POSITION WHEN THE DEVICE |
| WAS RUN OVER. THE ONLY DAMAGE APPEARS TO BE TO THE ELECTRONICS PORTION OF |
| THE DEVICE. A PRELIMINARY SWIPE WAS TAKEN AND NO CONTAMINATION WAS |
| DETERMINED. THE DEVICE IS BEING STORED AT THE LICENSEE'S FACILITY IN |
| EUGENE, OREGON AWAITING TO BE SENT BACK TO THE MANUFACTURER. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35949 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FLORIDA STATE WARNING POINT |NOTIFICATION DATE: 07/23/1999|
|LICENSEE: CAP ENGINEERING CONSULTANTS |NOTIFICATION TIME: 12:46[EDT]|
| CITY: WEBSTER REGION: 2 |EVENT DATE: 07/23/1999|
| COUNTY: SUMTER STATE: FL |EVENT TIME: 12:00[EDT]|
|LICENSE#: FL-2611-1 AGREEMENT: Y |LAST UPDATE DATE: 07/23/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |EDWARD MCALPINE R2 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: FLETCHER | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TROXLER MOISTURE DENSITY GAUGE FOUND IN WEBSTER, FL |
| |
| MELISSA SYLVEST, FL STATE WARNING POINT, REPORTED TO THE NATIONAL RESPONSE |
| CENTER THAT A TROXLER MOISTURE DENSITY GAUGE, SERIAL #26065, WAS FOUND BY |
| THE ROAD SIDE IN WEBSTER, FL. THE DEVICE DOES NOT APPEAR TO BE DAMAGED AND |
| IS BEING HELD BY THE WEBSTER POLICE DEPARTMENT. THE LICENSEE FOR THE DEVICE |
| IS CAP ENGINEERING CONSULTANTS. |
| |
| NATIONAL RESPONSE CENTER INCIDENT REPORT #492446. |
| |
| SEE EVENT #31161 FOR ADDITIONAL INFORMATION. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35950 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/23/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 12:51[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/23/1999|
+------------------------------------------------+EVENT TIME: 11:30[EDT]|
| NRC NOTIFIED BY: T. McKEE |LAST UPDATE DATE: 07/23/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE R1 |
|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 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION OF A MINOR SEWAGE SPILL |
| |
| The licensee notified the New York State Department of Environmental |
| Conservation of a 2-5 gallon sewage spill from the warehouse sewage pit to a |
| storm drain. |
| |
| The licensee will inform the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35951 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NEW YORK CITY DEPT OF HEALTH |NOTIFICATION DATE: 07/23/1999|
|LICENSEE: NEW YORK PRESBYTERIAN HOSPITAL |NOTIFICATION TIME: 13:20[EDT]|
| CITY: NEW YORK REGION: 1 |EVENT DATE: 07/22/1999|
| COUNTY: STATE: NY |EVENT TIME: 13:20[EDT]|
|LICENSE#: 52-2960-11 AGREEMENT: Y |LAST UPDATE DATE: 07/23/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JAMES NOGGLE R1 |
| |SCOTT MOORE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BORRI | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MISSING SHIPMENT OF 10 MILLICURIES OF IODINE-131 |
| |
| NEW YORK PRESBYTERIAN HOSPITAL, NEW YORK CITY, RECEIVED A SHIPMENT OF 10 |
| MILLICURIES OF IODINE -131 ON 07/20/99 FROM MDS NORDIAN, CANADA. THE SOURCE |
| APPEARS TO BE MISSING AS OF 07/22/99. HOSPITAL PERSONNEL ARE SEARCHING FOR |
| THE SHIPMENT AT THE HOSPITAL. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35952 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 07/23/1999|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 13:26[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/19/1999|
+------------------------------------------------+EVENT TIME: 09:45[EDT]|
| NRC NOTIFIED BY: MIKE WHALEN |LAST UPDATE DATE: 07/23/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |EDWARD MCALPINE R2 |
|10 CFR SECTION: | |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| A LICENSEE VOLUNTARY 24 HOUR NOTIFICATION IS BEING MADE TO REPORT AN INITIAL |
| LACK OF INDEPENDENT ANALYSIS OF BORON CONCENTRATION SAMPLES. |
| |
| Dissolved boron concentration of the spent fuel pool and of the water added |
| to the cavity of a sealed source storage cask is required to be within |
| limits specified in ISFSI Technical Specification Section 3.2.1, Table 3-1 |
| within 4 hours prior to commencing loading operations. The boron |
| concentration is determined using chemical analysis of two samples analyzed |
| by different individuals to reduce the risk that a single error could lead |
| to not meeting the LCO. |
| |
| By procedure, Sample 1 is obtained from the spent fuel pool and from the |
| cask pit by one technician. Sample 2 is then obtained from the spent fuel |
| pool and from the cask pit by a different technician. Sample 1 is to be |
| analyzed by the technician who obtained Sample 2 and vice versa. |
| |
| On 07/19/99, boron concentration sampling was performed prior to loading a |
| spent fuel cask. Technician 1 obtained both cask pit samples and Technician |
| 2 obtained both spent fuel pool samples. Technician 1 then analyzed both |
| cask pit samples and Technician 2 analyzed both spent fuel pool samples. |
| This is contrary to ISFSI Technical Specification Section 3.2.1. Upon |
| realizing the lack of independence in analyzing the samples, Technician 1 |
| analyzed the samples Technician 2 obtained and vice versa. Results of the |
| analysis indicated acceptable dissolved boron concentrations. |
| |
| The Licensee informed the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35953 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: OR DEPT OF HEALTH RAD PROTECTION |NOTIFICATION DATE: 07/23/1999|
|LICENSEE: SMURFIT NEWSPRINT COMPANY |NOTIFICATION TIME: 14:52[EDT]|
| CITY: OREGON CITY REGION: 4 |EVENT DATE: 07/07/1999|
| COUNTY: STATE: OR |EVENT TIME: 10:49[PDT]|
|LICENSE#: ORE-90296 AGREEMENT: Y |LAST UPDATE DATE: 07/23/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |ELMO COLLINS R4 |
| |SCOTT MOORE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: WRIGHT | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STUCK SHUTTER ON A K-RAY LEVEL DETECTOR |
| |
| ON 07/16/99, A SMURFIT NEWSPRINT COMPANY REPRESENTATIVE NOTIFIED THE OREGON |
| DEPARTMENT OF HEALTH RADIATION PROTECTION THAT THE SHUTTER ON A MODEL 7062B |
| K-RAY LEVEL DETECTOR AT THE SMURFIT NEWSPRINT COMPANY FACILITY IN OREGON |
| CITY, OREGON STUCK OPEN FOR UNKNOWN REASONS. THE DETECTOR IS LOCATED IN THE |
| #5 TMP STEAMING TUBE/TANK WHICH IS USED FOR PROCESSING PAPER. A TN |
| TECHNOLOGIES REPRESENTATIVE WILL GO TO THE PLANT TO REPLACE THE DETECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35954 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 07/23/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 17:04[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 07/23/1999|
+------------------------------------------------+EVENT TIME: 15:58[EDT]|
| NRC NOTIFIED BY: SIENCZAK |LAST UPDATE DATE: 07/23/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE R1 |
|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 Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTO REACTOR SCRAM FROM 100% POWER DUE TO A HIGH FLUX SIGNAL |
| |
| DURING POST MAINTENANCE TESTING OF THE MECHANICAL PRESSURE REGULATOR, |
| REACTOR PRESSURE OSCILLATIONS WERE EXPERIENCED AND AN AUTOMATIC REACTOR |
| SCRAM OCCURRED FROM 100% POWER DUE TO A HIGH FLUX SIGNAL. ALL CONTROL RODS |
| FULLY INSERTED AND NO SAFETY/RELIEF VALVES LIFTED. THE HIGH PRESSURE |
| COOLANT INJECTION SYSTEM STARTED AS EXPECTED AND INJECTED FOR APPROXIMATELY |
| 52 SECONDS BEFORE BEING SECURED. UNIT 1 IS STABLE IN HOT SHUTDOWN CONDITION |
| AND COOLDOWN IS IN PROGRESS. ALL SYSTEMS APPEARED TO FUNCTION, AS |
| DESIGNED. |
| |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35955 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/23/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:06[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/23/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 03:20[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 07/23/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |PATRICK HILAND R3 |
| DOCKET: 0707002 |LARRY CAMPER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM McCLEERY | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC SHUTDOWN OF AUTOCLAVE #2 STEAM SYSTEM DUE TO HIGH CONDENSATE |
| LEVEL |
| |
| AT 0320 ON 07/23/99, AUTOCLAVE #2, OPERATING IN MODE 2 (HEATING), |
| EXPERIENCED A SAFETY SYSTEM SHUTDOWN WHEN BOTH CONDENSATE HIGH LEVEL PROBES |
| ALARMED SHUTTING DOWN THE STEAM SYSTEM 20 MINUTES INTO THE HEATING CYCLE. |
| THIS ACTUATION PLACED THE AUTOCLAVE INTO MODE 7 (SHUTDOWN) AND WAS DECLARED |
| INOPERABLE BY THE PLANT SHIFT SUPERINTENDENT AT 0331. OPERATIONS PERSONNEL |
| FOLLOWED ESTABLISHED ALARM RESPONSE PROCEDURES AND VERIFIED THE HIGH LEVEL |
| ALARM ACTUATION AT 0430. AN ENGINEERING EVALUATION IS IN PROGRESS. |
| |
| THERE WAS NO LOSS OF HAZARDOUS OR RADIOACTIVE MATERIAL NOR RADIOACTIVE OR |
| RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. |
| |
| THE NRC RESIDENT INSPECTOR AND THE DOE SITE REPRESENTATIVE HAVE BEEN |
| NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35956 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 07/24/1999|
| UNIT: [] [2] [3] STATE: IL |NOTIFICATION TIME: 13:34[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 07/24/1999|
+------------------------------------------------+EVENT TIME: 09:20[CDT]|
| NRC NOTIFIED BY: GADBOIS |LAST UPDATE DATE: 07/24/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 57 Power Operation |57 Power Operation |
|3 N Y 68 Power Operation |68 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO ILLINOIS EPA |
| |
| THE LICENSEE NOTIFIED THE ILLINOIS EPA AS REQUIRED BY NPDES PERMIT STANDARD |
| CONDITION NO. 12(e)(1) OF AN UNANTICIPATED BYPASS OF THE DRESDEN STATION |
| COOLING POND. THIS OCCURRED DUE TO A LIGHTNING STRIKE THAT CAUSED THE LOSS |
| OF THE COOLING POND LIFT STATION. THE COOLING POND WAS PLACED ON BYPASS AT |
| 2241 CDT ON 07/23/99. LIFT STATION OPERATION WAS RESTORED AND THE COOLING |
| POND PLACED BACK ON INDIRECT OPEN CYCLE AT 0626 CDT ON 07/24/99. BOTH UNITS |
| WERE PREVIOUSLY DERATED DUE TO THERMAL DISCHARGE LIMITATIONS. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35957 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 07/24/1999|
| UNIT: [1] [] [] STATE: MD |NOTIFICATION TIME: 15:16[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 07/24/1999|
+------------------------------------------------+EVENT TIME: 14:38[EDT]|
| NRC NOTIFIED BY: PACE |LAST UPDATE DATE: 07/24/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE 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 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTO REACTOR TRIP FROM 100% POWER FOLLOWING A TURBINE TRIP. |
| |
| AN AUTO REACTOR TRIP OCCURRED FROM 100% POWER FOLLOWING A TURBINE TRIP WHICH |
| OCCURRED FOLLOWING LOSS OF UNIT TRANSFORMER U25,000-12. IT APPEARS THAT THE |
| TRANSFORMER FAULT PROTECTION ACTUATED DUE TO A POSSIBLE LIGHTNING STRIKE TO |
| THE TRANSFORMER. THE FIRE DELUGE SYSTEM FOR THE TRANSFORMER ACTUATED, BUT |
| THERE WAS NO EVIDENCE OF ANY FIRE, WITH THE EXCEPTION OF A SCORCHED PHASE |
| BUSHING WHICH MAY HAVE BEEN THE RESULT OF A LIGHTNING STRIKE. THERE IS NO |
| ESTIMATE OF THE EXTENT OF DAMAGE TO THE TRANSFORMER. ALL CONTROL RODS FULLY |
| INSERTED, NO ECCS INJECTION OCCURRED AND NO SAFETY/RELIEF VALVES APPEARED TO |
| HAVE LIFTED. THE CURRENT HEAT SINK IS THE MAIN CONDENSER. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35958 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 07/25/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 22:32[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 07/25/1999|
+------------------------------------------------+EVENT TIME: 20:21[CDT]|
| NRC NOTIFIED BY: WILLIAMS |LAST UPDATE DATE: 07/25/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PATRICK HILAND R3 |
|10 CFR SECTION: | |
|AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 87 Power Operation |87 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT ENTERED TECH SPEC 3.2.3 LCO ACTION STATEMENT |
| |
| AT 2021 CDT ON 07/25/99, THE "1B21-N500" PRESSURE TRANSMITTER INDICATION |
| DROPPED FROM 1000 PSIG TO INDICATED 600 PSIG REACTOR PRESSURE. THIS |
| TRANSMITTER IS THE PRIMARY PRESSURE TRANSMITTER TO THE ELECTROHYDRAULIC |
| SYSTEM (EHC). DUE TO THIS CHANGE IN PRESSURE INDICATION, THE BACKUP |
| TRANSMITTER TOOK CONTROL. IN THIS LINEUP (BACKUP TRANSMITTER IN CONTROL OF |
| THE EHC), THERE IS NO OTHER BACKUP TRANSMITTER AVAILABLE AND PROCEDURE |
| "LOA-EH-101" STATES THAT THIS CONDITION IS AN UNANALYZED CONDITION AND THE |
| PLANT IS TO ENTER TS 3.2.3. TS 3.2.3 REQUIRES THE REACTOR TO BE <25% POWER |
| WITHIN 4 HOURS. THIS CONDITION WAS NOT DETERMINED TO BE AN UNANALYZED |
| CONDITION UNTIL 2045 CDT ON 07/25/99 UTILIZING THE ABOVE PROCEDURE AND THE |
| UFSAR. THE PROBLEM WITH THE TRANSMITTER IS BEING INVESTIGATED TO DETERMINE |
| WHY IT DOES NOT INDICATE 1000 PSIG. |
| |
| THE RESIDENT INSPECTOR WILL BE INFORMED. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021