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
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|Power Reactor |Event Number: 36544 |
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| 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 |
| | |
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EVENT TEXT
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| 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. |
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|Power Reactor |Event Number: 36545 |
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| 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
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| 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) |
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|Power Reactor |Event Number: 36546 |
+------------------------------------------------------------------------------+
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| 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
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| 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. |
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|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
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| 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. |
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|Power Reactor |Event Number: 36548 |
+------------------------------------------------------------------------------+
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| 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. |
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