Event Notification Report for January 28, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/27/2000 - 01/28/2000

                              ** EVENT NUMBERS **

36552  36607  36621  36629  36630  36631  36632  36633  36634  36635  36636  36637 
36638  

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36552       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 12/30/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 21:45[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        12/30/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:30[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/27/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |BRUCE BURGESS        R3      |
|  DOCKET:  0707001                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC WALKER                  |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NOTE:  THIS EVENT IS A CONTINUATION OF EVENT #35790.  (Refer the event       |
| #36018 and event #36605 for similar events at Portsmouth.)                   |
|                                                                              |
| At 1130 CST on 12/30/99, the Plant Shift Superintendent (PSS) was notified   |
| that during walkdowns of the High Pressure Fire Water System in C-337, a     |
| total of 13 corroded sprinkler heads were discovered in System B-2.  The     |
| system was declared inoperable and actions were taken as required by the     |
| technical safety requirement.  The PSS determined that an update to this     |
| event report is required.                                                    |
|                                                                              |
| The NRC Resident Inspector has been notified of this event.                  |
|                                                                              |
| * * * UPDATE 2233EST ON 1/12/00 FROM ERIC WALKER TO S. SANDIN * * *          |
|                                                                              |
| At 0910 on 1/12/00 the Plant Shift Superintendent (PSS) was notified that    |
| during walk downs of the High Pressure Fire Water (HPFW) systems in C-337,   |
| two adjacent corroded heads were discovered on system B-10. Per Engineering  |
| Notice C-822-99-047 Rev. 2, the criteria necessary for system operability    |
| was not being met. The system was declared Inoperable and actions were taken |
| as required by the TSR. The PSS determined that an update to this event      |
| report is required.                                                          |
|                                                                              |
| It has been determined that this event is reportable under 10CFR76.120(c)(2) |
| as an event in which equipment is disabled or fails to function as           |
| designed.                                                                    |
|                                                                              |
| The NRC Resident Inspector has been notified of this event. Notified         |
| R3DO(Clayton) and NMSS(Haughney).                                            |
|                                                                              |
|                                                                              |
| ***  UPDATE ON 1/21/00 @ 2306 BY UNDERWOOD TO GOULD  ***                     |
|                                                                              |
| At 1100 on 1/21/00, the Plant Shift Superintendent (PSS) was notified that   |
| during walk downs of the High Pressure Fire Water (HPFW) systems in C-337,   |
| thirteen corroded heads were discovered on system D-3.  This system was      |
| previously inspected on 6/24/99.   Also, at 1640 on 1/21/00, the PSS was     |
| notified that during walk downs of the HPFW systems in C-331, three adjacent |
| corroded heads were discovered on system 12.  This system was previously     |
| inspected by Fire Services Personnel on 4/10/99.  Per Engineering Notice     |
| C-822-99-047 Rev. 2, the criteria necessary for system operability was not   |
| being met.  The systems were declared inoperable and actions were taken as   |
| required by the TSR.  The PSS determined that an update to this event report |
| is required.                                                                 |
|                                                                              |
| The NRC Resident Inspector has been notified of this event.                  |
|                                                                              |
| Reg 3 RDO(Hills) was notified.                                               |
|                                                                              |
| * * * UPDATE 1549 1/27/2000 FROM WHITE TAKEN BY STRANSKY * * *               |
|                                                                              |
| "At 1500 on 1/26/00, the Plant Shift Superintendent (PSS) was notified that  |
| during walk downs of the High Pressure Fire Water (HPFW) systems in C-337,   |
| eight corroded heads were discovered on system D-12. This system was         |
| previously inspected on 8/28/99. Per Engineering Notice C-822-99-047 Rev. 2, |
| the criteria necessary for system operability was not being met. The systems |
| were declared inoperable and actions were taken as required by the TSR. The  |
| PSS determined that an update to this event report is required."             |
|                                                                              |
| The NRC resident inspector has been notified of this event.                  |
|                                                                              |
| Notified R3DO (Phillips).                                                    |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36607       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ZION                     REGION:  3  |NOTIFICATION DATE: 01/18/2000|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 19:15[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/18/2000|
+------------------------------------------------+EVENT TIME:        18:02[CST]|
| NRC NOTIFIED BY:  R. T. THORTON                |LAST UPDATE DATE:  01/27/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID HILLS          R3      |
|10 CFR SECTION:                                 |ROBERTA WARREN       IAT     |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |JIM CREED            IAT     |
|                                                |JIM BELANGER         IAT     |
|                                                |DICK ROSANO          IAT     |
|                                                |STEVE REYNOLDS       R3      |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Decommissioned   |0        Decommissioned   |
|2     N          N       0        Decommissioned   |0        Decommissioned   |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SECURITY REPORT                                                              |
|                                                                              |
| UNSUBSTANTIATED BOMB THREAT.  COMPENSATORY MEASURES TAKEN.  LICENSEE         |
| INFORMED THE LOCAL POLICE DEPARTMENT.                                        |
|                                                                              |
| * * * RETRACTION 1533 1/27/2000 FROM NOLDEN TAKEN BY STRANSKY * * *          |
|                                                                              |
| After review of NRC Regulatory Guide 5.62, the licensee has determined that  |
| this event was not reportable. Notified R3DO (Phillips).                     |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36621       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 01/25/2000|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 06:44[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        01/25/2000|
+------------------------------------------------+EVENT TIME:        06:10[EST]|
| NRC NOTIFIED BY:  CORNAX                       |LAST UPDATE DATE:  01/27/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN ROGGE           R1      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(1)(ii)(A)  UNANALYZED COND OP     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       99       Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BROKEN WINDOW IN A HIGH ENERGY LINE BREAK DOOR PLACES THE PLANT IN AN        |
| UNANALYZED CONDITION                                                         |
|                                                                              |
| A broken window in a High Energy Line Break Door which is located between    |
| the Main Feed Regulating Valve Room and the Auxiliary Boiler Feed Pump Room  |
| places the plant in an unanalyzed condition.  Maintenance is fabricating a   |
| metal replacement part to cover the opening.  The door is supposed to remain |
| closed at all times when the plant is above 350 degrees F.                   |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
|                                                                              |
| * * * RETRACTION 1259 1/27/2000 TAKEN BY STRANSKY * * *                      |
|                                                                              |
| "Indian Point has performed an engineering evaluation of the broken window   |
| in the High Energy Line Break door located between the Main Feed Regulating  |
| Valve room and the Auxiliary Boiler Feed Pump room and determined that the   |
| equipment in the Auxiliary Boiler Feed Pump room would have maintained its   |
| environmental qualification and the plant would have remained in an analyzed |
| condition even if the window was entirely missing. Therefore, this event has |
| been retracted."                                                             |
|                                                                              |
| The licensee will inform the NRC resident inspector of this retraction.      |
| Notified R1DO (Rogge).                                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36629       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 01/27/2000|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 11:35[EST]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        01/27/2000|
+------------------------------------------------+EVENT TIME:        09:00[EST]|
| NRC NOTIFIED BY:  BANDHAVER                    |LAST UPDATE DATE:  01/27/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|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 TO FLORIDA FISH AND WILDLIFE CONSERVATION COMMISSION    |
|                                                                              |
| A GREEN SEA TURTLE(AN ENDANGERED SPECIES) WAS FOUND IN THE INTAKE.  THE      |
| TURTLE WILL BE HELD FOR A DAY TO ENSURE ITS HEALTH AND THEN RELEASED IN      |
| ACCORDANCE WITH THE FISH AND WILDLIFE CONSERVATION COMMISSION DIRECTIONS.    |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36630       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 01/27/2000|
|    UNIT:  [1] [] []                 STATE:  GA |NOTIFICATION TIME: 12:09[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        01/26/2000|
+------------------------------------------------+EVENT TIME:        22:38[EST]|
| NRC NOTIFIED BY:  MUSGROVE                     |LAST UPDATE DATE:  01/27/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FAILURE OF PRIMARY CONTAINMENT ISOLATION VALVE TO CLOSE ON A LOW REACTOR     |
| PRESSURE SIGNAL.                                                             |
|                                                                              |
| PRIMARY CONTAINMENT ISOLATION VALVE "1E51-F008" DID NOT CLOSE ON A LOW       |
| REACTOR PRESSURE SIGNAL DUE TO INSTRUMENT "1E51-N685C" BEING INOPERABLE.     |
| THE OTHER VALVE IN THIS LINE, VALVE "1E51-F007", DID CLOSE TO ISOLATE THE    |
| PENETRATION.  THE "1E51-F008" VALVE WAS CLOSED AS DIRECTED BY THE SHUTDOWN   |
| PROCEDURE "34G0-OPS-013-1S".  THIS EVENT IS BEING INVESTIGATED TO DETERMINE  |
| THE ROOT CAUSE.  THE REPORTABILITY OF THE EVENT WAS NOT DETERMINED AT THE    |
| TIME OF THE OCCURRENCE.                                                      |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED.                                     |
|                                                                              |
| [HOO NOTE:  SEE RELATED EN 36625.]                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36631       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 01/27/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 14:12[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        01/26/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        14:45[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/27/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MONTE PHILLIPS       R3      |
|  DOCKET:  0707002                              |                     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MCCLEERY                     |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24 HOUR 91-01 BULLETIN RESPONSE                                              |
|                                                                              |
| AT APPROXIMATELY 1445 HRS @ 1/26/00, ELEVEN (11) BAGS WITH MISCELLANEOUS     |
| CONTENTS WERE DISCOVERED IN THE X-103 HEALTH PHYSICS SOURCE VAULT.  THREE    |
| (3) OF THE ELEVEN ITEMS CONTAINED GREATER THAN 1% U-235 WITH THE HIGHEST     |
| ASSAY BEING 52.1 %.  THE TOTAL GRAM CONTENT OF ALL THREE ITEMS INCLUDING     |
| ERROR IS 158.5 g U-235 FOR 52% ASSAY (MOST LIMITING).   ALL ELEVEN ITEMS     |
| WERE PLACED INTO TWO (2) APPROVED CONTAINERS WHICH WERE MOVED TO AN APPROVED |
| STORAGE FACILITY.                                                            |
|                                                                              |
|                                                                              |
| THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                       |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT.   |
|                                                                              |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED AND THE DOE REPRESENTATIVE WILL BE   |
| NOTIFIED                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36632       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 01/27/2000|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 15:06[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/27/2000|
+------------------------------------------------+EVENT TIME:        11:22[CST]|
| NRC NOTIFIED BY:  FRED SCHIZAS                 |LAST UPDATE DATE:  01/27/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR WATER CLEANUP ISOLATION WHILE PLACING SYSTEM IN SERVICE              |
|                                                                              |
| "During initial repressurization of the reactor water cleanup system (RWCU)  |
| after the maintenance outage, the control room received channel 'A' and 'B'  |
| RWCU high flow alarm (<=191% of rated flow) and subsequent Group 3 isolation |
| (closure of RWCU-MOV-M015 and RWCU-MOV-M018 inboard / outboard primary       |
| containment isolation valves). This actuation occurred while the operator    |
| was throttling open RWCU-M018.                                               |
|                                                                              |
| The Group 3 was verified per G.O.P. 2.1.22 (Recovery From Group Isolations)  |
| and following recovery, system flow was restored."                           |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36633       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 01/27/2000|
|    UNIT:  [] [2] []                 STATE:  CT |NOTIFICATION TIME: 15:10[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        01/27/2000|
+------------------------------------------------+EVENT TIME:        14:57[EST]|
| NRC NOTIFIED BY:  STEVE BAKER                  |LAST UPDATE DATE:  01/27/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN ROGGE           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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO SECONDARY SYSTEM TRANSIENT                        |
|                                                                              |
| Operators manually tripped the unit from 100% power due to decreasing steam  |
| generator water levels caused by a decrease in feedwater flow. Feedwater     |
| flow decreased due to a transient in a feedwater heater string. All control  |
| rods inserted following the trip. Operators also manually initiated the      |
| auxiliary feedwater system to restore steam generator water levels (a        |
| confirmatory automatic initiation signal was received). The unit is          |
| currently stable in Hot Standby.  All systems functioned as expected.        |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36634       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 01/27/2000|
|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 15:38[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        01/27/2000|
+------------------------------------------------+EVENT TIME:        12:01[EST]|
| NRC NOTIFIED BY:  DARLENE BROCK                |LAST UPDATE DATE:  01/27/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| EXCESSIVE LEAKAGE THROUGH CONTAINMENT ISOLATION VALVE                        |
|                                                                              |
| "On 1/27/00 at 1201 hours, as-found 10CFR50 Appendix J Type C leakage        |
| testing of the outside containment trip valve 2-DA-TV-200B was determined to |
| be greater than 0.6 La. Leakage was determined to be approximately 182 scfh  |
| versus total minimum pathway leakage acceptance criteria of 180 scfh.        |
|                                                                              |
| "On 1/25/00 the inside containment trip valve 2-DA-TV-200A for the same      |
| penetration was replaced due to an unsatisfactory 1ST stroke time. Removal   |
| and installation of the valve was less than one hour in duration. Following  |
| replacement of the valve, Type C leakage was determined to be satisfactory   |
| for 2-DA-TV-200A, however, excessive leakage was suspected for the outside   |
| trip valve 2-DA-TV-200B.                                                     |
|                                                                              |
| "By testing conducted on 1/27/00, it was confirmed that during the timeframe |
| of 2-DA-TV-200A replacement, a condition which alone could have prevented    |
| the fulfillment of the safety function needed to control the release of      |
| radioactive material existed.                                                |
|                                                                              |
| "Currently containment integrity is being maintained by closure and          |
| deactivation of 2-DA-TV-200A in accordance with the station Technical        |
| Specification. Following replacement of 2-DA-TV-200A on 1/25/00, Type C      |
| testing was performed with satisfactory results (less than 1 scfh).          |
| Currently total minimum pathway leakage is approximately 3 scfh.             |
|                                                                              |
| This report is being made pursuant 10CFR50.72(b)(2)(iii)."                   |
|                                                                              |
| The licensee has informed the NRC resident inspector of this event.          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   36635       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  USAF RADIOISOTOPE COMMITTEE          |NOTIFICATION DATE: 01/27/2000|
|LICENSEE:  USAF RADIOISOTOPE COMMITTEE          |NOTIFICATION TIME: 16:51[EST]|
|    CITY:  KEESLER AFB              REGION:  4  |EVENT DATE:        01/27/2000|
|  COUNTY:                            STATE:  LA |EVENT TIME:        15:00[CST]|
|LICENSE#:  42-23539-AF           AGREEMENT:  Y  |LAST UPDATE DATE:  01/27/2000|
|  DOCKET:  03028641                             |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GAIL GOOD            R4      |
|                                                |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MAJ. HICKS                   |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MISSING CALIBRATION SOURCE                                                   |
|                                                                              |
| On 1/26/00, the Keesler AFB Radiation Safety Officer (RSO) was unable to     |
| locate a 1.37 �Ci Pu-239 calibration source during a routine inventory of    |
| Wolfe Hall. During the subsequent investigation, the Wolfe Hall RSO reported |
| that the source was to have been transferred to Kelly AFB in Texas, but it   |
| had inadvertently been shipped to McLellan AFB in California. However, the   |
| McLellan AFB transportation office has no record of receiving the source.    |
| The Keesler AFB RSO will continue to attempt to locate the source.           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36636       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 01/27/2000|
|    UNIT:  [1] [2] []                STATE:  TX |NOTIFICATION TIME: 17:12[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/27/2000|
+------------------------------------------------+EVENT TIME:        12:50[CST]|
| NRC NOTIFIED BY:  PAUL COX                     |LAST UPDATE DATE:  01/27/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO OIL SHEEN                                        |
|                                                                              |
| The licensee notified the Texas Natural Resource Conservation Commission and |
| the US DOT National Response Center regarding the appearance of an oil sheen |
| near the circulating water discharge. The licensee believes that the oil is  |
| residue from recent paving activities that has been washed out due to heavy  |
| rains. The licensee has deployed absorbent materials to control the spill.   |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36637       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE               REGION:  4  |NOTIFICATION DATE: 01/27/2000|
|    UNIT:  [] [2] [3]                STATE:  CA |NOTIFICATION TIME: 19:13[EST]|
|   RXTYPE: [1] W-3-LP,[2] CE,[3] CE             |EVENT DATE:        01/27/2000|
+------------------------------------------------+EVENT TIME:        15:30[PST]|
| NRC NOTIFIED BY:  A. BOLYEN                    |LAST UPDATE DATE:  01/27/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNITS OUTSIDE OF DESIGN BASIS DUE TO WORDING OF UFSAR                        |
|                                                                              |
| "This notification is for San Onofre Units 2 and 3 and is being made in      |
| accordance with 10CFR50.72(b)(1)(ii)(B).                                     |
|                                                                              |
| "Southern California Edison was performing a review of plant drawings and    |
| noticed a potential discrepancy between some circuit designs and the         |
| specific wording used in the Updated Final Safety Analysis Report (UFSAR) to |
| describe the design for those circuits. Further investigation of the         |
| affected components revealed that certain functions appear to not fully meet |
| the separation criteria of Regulatory Guide 1.75, 'Physical Independence of  |
| Electrical Systems.' These circuits include relays for portions of some      |
| Engineered Safety Features (e.g., boric acid makeup pumps and input voltage  |
| to one of the four loss-of-voltage-signal circuits). The UFSAR for Units 2   |
| and 3 indicates these systems comply with IEEE-279, 1971, 'Criteria for      |
| Protection Systems for Nuclear Power Generation Stations' which is           |
| referenced by Regulatory Guide 1.75. Consequently, at 1530 PDT, SCE          |
| concluded this condition was reportable in accordance with                   |
| 10CFR50.72(b)(1)(ii)(B) as a condition 'outside the design basis of the      |
| plant.'                                                                      |
|                                                                              |
| "SCE has confirmed that the affected components remain capable of performing |
| their intended safety functions and, therefore, concludes there is no safety |
| significance to this occurrence.                                             |
|                                                                              |
| "At the time of this report. Unit 1 remains permanently shutdown, and Units  |
| 2 and 3 are operating at about 100% power. SCE will notify the NRC resident  |
| inspectors of this condition and provide them with a copy of this report."   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36638       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 01/28/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 05:14[EST]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        01/28/2000|
+------------------------------------------------+EVENT TIME:        02:40[CST]|
| NRC NOTIFIED BY:  DARYL CLARK                  |LAST UPDATE DATE:  01/28/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MONTE PHILLIPS       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          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH EMERGENCY DIESEL GENERATORS INOPERABLE DURING CORE ALTERATIONS          |
|                                                                              |
| "On 1/28/00 at 0005 hrs. the U- 2 Emergency Diesel Generator was found to be |
| inoperable due to the diesel generator room vent fan selector switch being   |
| selected to the alternate feed. The 1/2 Emergency Diesel Generator was       |
| inoperable due to Division I electrical system refuel outage work. Core      |
| alterations were in progress.                                                |
|                                                                              |
| "Per Tech Spec 3.9.B, one diesel generator must be operable in Mode 5, and   |
| when handling irradiated fuel in the secondary containment.                  |
|                                                                              |
| "The switch was aligned to the normal position and vent fan operation was    |
| verified within approximately 15 minutes to restore the U-2 diesel generator |
| to an operable status. An internal investigation is commencing. Although     |
| both the 1/2 and U-2 EDGs were inoperable, both diesels remained available   |
| for operation.                                                               |
|                                                                              |
| "This event is being reported as required by 10CFR50.72(b)(2)(iii)(D), an    |
| event which alone could have prevented the fulfillment of a safety function  |
| needed to mitigate the consequences of an accident."                         |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+


Page Last Reviewed/Updated Thursday, March 12, 2020