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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  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   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.                            |
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