Event Notification Report for December 30, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/29/1999 - 12/30/1999 ** EVENT NUMBERS ** 36544 36545 36546 36547 36548 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36544 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 12/29/1999| | UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 06:15[EST]| | RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 12/29/1999| +------------------------------------------------+EVENT TIME: 04:20[CST]| | NRC NOTIFIED BY: DARYL NOHR |LAST UPDATE DATE: 12/29/1999| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |BRUCE BURGESS R3 | |10 CFR SECTION: | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N Y 90 Power Operation |80 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI INOPERABLE | | | | During QCOS 2300-28 'HPCI Turning Gear Logic Functional Test' the HPCI | | turning gear failed to engage. The test was stopped and HPCI was placed on | | the turning gear from a normal standby lineup and removed from the turning | | gear using QCOP 2300-13 'HPCI Turning Gear Operation'. Per analysis the | | HPCI turbine must be able to be remotely placed on the turning gear. Since | | HPCI failed to go on gear during the logic test it was declared inoperable | | at 0420. A 14 day LCO was centered per Tech Spec 3.5.A action 3. | | | | The Licensee will notify the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36545 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 12/29/1999| | UNIT: [] [] [3] STATE: SC |NOTIFICATION TIME: 06:23[EST]| | RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 12/29/1999| +------------------------------------------------+EVENT TIME: 05:55[EST]| | NRC NOTIFIED BY: DAVID YONGUE |LAST UPDATE DATE: 12/29/1999| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: UNU |CHRIS CHRISTENSEN R2 | |10 CFR SECTION: |JACK STROSNIDER NRR | |AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |JOSEPH GIITTER IRO | | |RISHE FEMA | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | |3 N Y 90 Power Operation |80 Power Operation | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED AT 0555 DUE TO AN IDENTIFIED REACTOR COOLANT LEAK. | | | | THE LETDOWN STORAGE TANK BYPASS VALVE (3HP14) FAILED IN AN INTERMEDIATE | | POSITION. APPROXIMATELY 45 GPM OF RCS WATER IS BEING BLED THROUGH THE | | VALVE INTO THE DE-LITH DEMINERALIZERS. THE PLANT IS STABLE AT 80% POWER. | | VALVE 3HP14 IS AN MOV ON A 2 1/2" LINE. THE 45 GPM OF FLOW IS CONSIDERED | | "RECOVERABLE" RCS LEAKAGE. | | | | THE EVENT OCCURRED AT 0555 AND THE CURRENT LINEUP WAS REACHED AT 0604. THE | | LICENSEE WILL REMAIN IN THE UNUSUAL EVENT UNTIL THEIR ENGINEERING DEPARTMENT | | DETERMINES THAT THEY CAN REMAIN IN THIS LINEUP WHILE REPAIRS ARE MADE TO | | 3HP14. | | | | THIS EVENT IS SIMILAR TO EVENT 36543 WHICH OCCURRED ON 12/27/99. THAT EVENT | | LED TO REPAIRS ON 3HP14. THE MOTOR HAD BECOME UNCOUPLED FROM THE VALVE AND | | WAS REPAIRED. IT IS NOT KNOWN NOW WHETHER THE SAME FAILURE MECHANISM HAS | | BEEN REPEATED DURING THE CURRENT EVENT. | | | | THE RESIDENT INSPECTOR HAS BEEN NOTIFIED ALONG WITH STATE AND LOCAL | | AGENCIES. | | THERE WILL BE NO PRESS RELEASE. | | | | * * * UPDATE AT 0715 ON 12/29/99, BY BALDWIN, TAKEN BY WEAVER * * * | | THE UNUSUAL EVENT WAS TERMINATED AT 0713. THE LICENSEE WILL INFORM THE NRC | | RESIDENT INSPECTOR. THE HOO NOTIFIED R2DO (CHRISTENSEN); EO (STROSNIDER); | | IRO (GIITTER); FEMA (RISHE) | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36546 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 12/29/1999| | UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 16:59[EST]| | RXTYPE: [1] W-3-LP |EVENT DATE: 12/29/1999| +------------------------------------------------+EVENT TIME: 16:30[EST]| | NRC NOTIFIED BY: APRIL RICE |LAST UPDATE DATE: 12/29/1999| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CHRIS CHRISTENSEN R2 | |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 +------------------------------------------------------------------------------+ | SOME KAOWOOL FIRE BARRIERS OUTSIDE 10CFR50 APPENDIX R DESIGN BASIS | | | | "V.C. SUMMER HAS BEEN PERFORMING CONFIRMATORY TESTING ON KAOWOOL TRIPLE WRAP | | FIRE BARRIERS BASED ON SECY 99-204 ISSUES. PRELIMINARY RESULTS INDICATE | | THAT SOME CABLE/CONDUIT APPLICATIONS DO NOT MEET APPENDIX R III.G.2 | | REQUIREMENTS (FREE OF FIRE DAMAGE FOR ONE HOUR). THESE APPLICATIONS INCLUDE | | SMALL OPEN AIR CONDUIT (LESS THAN OR EQUAL TO 1"), AIR DROPS AND SMALL CABLE | | TRAYS (LESS THAN OR EQUAL TO 6" x 6"). OTHER APPLICATIONS PERFORMED | | ACCEPTABLY BASED ON PRELIMINARY REVIEW OF THE TEST DATA. V.C. SUMMER IS | | CURRENTLY COMPARING THE TEST CONFIGURATIONS TO ACTUAL PLANT CONFIGURATIONS | | TO DETERMINE AFFECTED AREAS. AS A CONSERVATIVE MEASURE A ROVING FIRE WATCH | | WAS ESTABLISHED ON ALL APPENDIX R AREAS UTILIZING KAOWOOL. ADDITIONAL | | ACTIONS WILL BE BASED ON FURTHER ENGINEERING EVALUATIONS." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36547 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 12/29/1999| | UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 17:10[EST]| | RXTYPE: [1] W-4-LP |EVENT DATE: 12/29/1999| +------------------------------------------------+EVENT TIME: 15:50[CST]| | NRC NOTIFIED BY: ROBERT WALTERS |LAST UPDATE DATE: 12/29/1999| | HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |GARY SANBORN R4 | |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 1-HOUR SECURITY REPORT INVOLVING HISTORICAL ACCESS AUTHORIZATION PROGRAM | | VIOLATION | | | | "During performance of a Plant Evaluation Checklist (PEC OB 99-1157) on the | | NRC Performance Indicator for Physical Protection Area a historical error | | was discovered pertaining [to] access authorization. It was discovered that | | unescorted access was authorized to an individual, from 11/10/95 to 1/16/96. | | However on 1/11/96 information was received that had it been properly | | investigated would have caused denial of unescorted access at that time. | | | | "This event is reportable as a one-hour report pursuant to 10 CFR 73.71 as | | an Access Authorization (AA) program violation as stated in an NRC letter | | from LeMoine J. Cunningham, Chief Safeguards Branch USNRC to the NRC Regions | | chief, dated May 19, 1995. In the letter Mr. Cunningham states that events | | involving AA program failure are reportable, and a 30 day written report | | required." | | | | The licensee will inform the NRC resident inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36548 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 12/30/1999| | UNIT: [] [2] [] STATE: GA |NOTIFICATION TIME: 05:53[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/30/1999| +------------------------------------------------+EVENT TIME: 04:56[EST]| | NRC NOTIFIED BY: LEE MANSFIELD |LAST UPDATE DATE: 12/30/1999| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CHRIS CHRISTENSEN 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 N N 0 Startup |0 Hot Standby | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP FROM MODE TWO | | | | "Plant Vogtle Unit 2 was in a reactor startup following repair of a | | Feedwater Heater. During withdrawal of Control Bank B to 85 steps, Control | | Bank B rod B6 became misaligned from Its bank by Digital Rod position | | indication System (DRPI) indication and the demand step counters. The Rod | | Control System Malfunction abnormal operating procedure was entered and the | | reactor was manually tripped at 0456 hours EST due to a misalignment of | | greater than 12 steps between DRPI and the demand step counters. All rods | | inserted as expected during the trip and no other anomalies were noted. The | | reactor is currently stable in Mode 3." | | | | The licensee informed the NRC resident inspector. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021