United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2000

Event Notification Report for September 19, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/18/2000 - 09/19/2000

                              ** EVENT NUMBERS **

37307  37333  37338  37339  37340  37341  37342  37343  37344  37345  37346  

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37307       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COMMONWEALTH OF KENTUCKY             |NOTIFICATION DATE: 09/11/2000|
|LICENSEE:  COMMONWEALTH OF KENTUCKY             |NOTIFICATION TIME: 17:21[EDT]|
|    CITY:  LEXINGTON                REGION:  2  |EVENT DATE:        09/11/2000|
|  COUNTY:                            STATE:  KY |EVENT TIME:        06:00[CDT]|
|LICENSE#:  201-142-51            AGREEMENT:  Y  |LAST UPDATE DATE:  09/18/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |KERRY LANDIS         R2      |
|                                                |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  VICKI JEFFS                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - STOLEN GAUGE                                        |
|                                                                              |
| "On September 11, 2000, Fuller, Mossbarger, Scot and May Engineers, Inc.,    |
| reported a stolen moisture/density gauge.  The gauge was a Troxler 3440,     |
| serial number 24606, containing an 8 millicurie cesium-137 and a 40          |
| millicurie americium-241 source.                                             |
|                                                                              |
| "The gauge was stolen sometime between 12:00 am. and 6:00 a.m. on September  |
| 11 from an employee's residence located in Lexington, KY.  The police have   |
| been notified.  The employee had stored the gauge, in its transport          |
| container, in his garage.  He put the gauge, in its transport container in   |
| the bed of his truck at about midnight in order to be ready to leave for the |
| job Site the next morning.  One of the owners of the company stated that the |
| container was locked to the bed of the truck with a chain and padlock.  The  |
| thief used a hacksaw to cut the chain and remove the transport container     |
| with the gauge inside.                                                       |
|                                                                              |
| "The owner stated he believed the source rod to also be locked and that the  |
| employee would have still have the keys to this lock."                       |
|                                                                              |
| * * * UPDATE 1133 9/18/2000 FROM VICKI JEFFS VIA FACSIMILE * * *             |
|                                                                              |
| "The gauge, Troxler 3440, S/N 24606, was found, undamaged, on the side of    |
| the road. The licensee now has possession of it. Licensee was cited for      |
| improper gauge storage."                                                     |
|                                                                              |
| Notified R2DO (Cahill).                                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37333       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 09/16/2000|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 23:43[EDT]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        09/16/2000|
+------------------------------------------------+EVENT TIME:        23:15[EDT]|
| NRC NOTIFIED BY:  LEON GAGNE                   |LAST UPDATE DATE:  09/18/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |STEPHEN CAHILL       R2      |
|10 CFR SECTION:                                 |JOHN ZWOLINSKI       NRR     |
|AAEC                                            |FRANK CONGEL         IRO     |
|                                                |AUSTIN               FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       99       Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT - HURRICANE WARNING                                            |
|                                                                              |
| The licensee declared an unusual event at 2315 due to a hurricane warning    |
| being declared for Citrus County, Florida.   Further actions will be taken   |
| depending upon the direction Hurricane Gordon takes in the next 24 hours.    |
| The licensee intends to remain at power and will continue to evaluate this   |
| storm.                                                                       |
|                                                                              |
| The licensee notified both state and local governments of the declaration as |
| well as the NRC resident inspector.                                          |
|                                                                              |
| * * * UPDATE AT 0049 ON 9/18/00 BY GAGNEY, RECEIVED BY WEAVER * * *          |
|                                                                              |
| The licensee exited the unusual event at 0035.  The hurricane warning is no  |
| longer in effect.  The storm caused no damage at the plant and it continues  |
| to operate at full power.                                                    |
|                                                                              |
| The licensee notified both state and local governments of the declaration as |
| well as the NRC resident inspector.                                          |
|                                                                              |
| HOO notified FEMA (CIBOCH); RDO (CAHILL); EO (ZWOLINSKI); IRO(CONGEL)        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37338       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE                   REGION:  2  |NOTIFICATION DATE: 09/18/2000|
|    UNIT:  [1] [] []                 STATE:  GA |NOTIFICATION TIME: 06:16[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/18/2000|
+------------------------------------------------+EVENT TIME:        04:50[EDT]|
| NRC NOTIFIED BY:  KEITH POPE                   |LAST UPDATE DATE:  09/18/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |STEPHEN CAHILL       R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH TRAINS OF RHR (RECIRC CAPABILITY) INOPERABLE FOR APPROXIMATELY SEVEN    |
| HOURS                                                                        |
|                                                                              |
| "While placing RHR Train'B' in shutdown cooling during a refueling outage    |
| the pump minimum flow valve did not close as expected.   Investigation       |
| revealed that the mini-flow transmitter 1 FIS-0611 was isolated causing the  |
| valve 1 FV0611 to remain open with RHR flow in excess of setpoint that would |
| cause the valve to close.   Work was performed on August 29, 2000, to        |
| calibrate this transmitter.   On September 9, 2000,  RHR Train 'A' seal      |
| cooler was isolated for maintenance rendering both trains of RHR inoperable  |
| for 6 hours and 54 minutes.  The Cold leg injection capability from RHR      |
| Train 'A' remained available during this time. The Cold leg recirculation    |
| capability during these inoperabilities was not available.  This would have  |
| required entry into T. S. 3.0.3.                                             |
|                                                                              |
| "RHR Train 'B' mini-flow transmitter 1FIS-0611 was discovered isolated       |
| causing the valve 1FV0611 to remain open with RHR flow in excess of setpoint |
| that would cause the valve to close.  The transmitter has been returned to   |
| service and the valve 1 FV0611 is operating properly."                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37339       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 09/18/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 06:47[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        09/18/2000|
+------------------------------------------------+EVENT TIME:        05:03[EDT]|
| NRC NOTIFIED BY:  MICKLOW                      |LAST UPDATE DATE:  09/18/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES TRAPP          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        N       0        Startup          |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DURING PLANT SHUTDOWN                                 |
|                                                                              |
| "A plant shutdown was in progress for a refueling outage, RCS pressure was   |
| at 2236 psig, Tavg at 541F.  Power as indicated on intermediate range        |
| channels N35 & N36 was 4 x10 minus 12 amps and 7.5 x 10 minus 11 amps,       |
| respectively.   Control room operator was in the process of driving control  |
| rods to 5 steps on Bank A, when P-6 permissive reset.  Coincident with P-6   |
| reset, a control power fuse blew on IR channel N-36, causing a Rx trip from  |
| 1/2 IR channels high.  All rods fully inserted on the trip.  Cause of the    |
| blown fuse is under investigation and plant shutdown will continue using     |
| normal operating procedures."                                                |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37340       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NORTH CAROLINA DIV OF RAD HEALTH     |NOTIFICATION DATE: 09/18/2000|
|LICENSEE:  WATAUGA REGIONAL MEDICAL CENTER      |NOTIFICATION TIME: 10:12[EDT]|
|    CITY:  BOONE                    REGION:  2  |EVENT DATE:        09/17/2000|
|  COUNTY:                            STATE:  NC |EVENT TIME:        12:00[EDT]|
|LICENSE#:  095-0491-2            AGREEMENT:  Y  |LAST UPDATE DATE:  09/18/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |STEPHEN CAHILL       R2      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JEFFRIES                     |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| A member of the cleaning staff at Watauga Regional Medical Center in Boone,  |
| NC removed the linens from the room of an I -131 patient in isolation.  The  |
| mistake was caught by one of the nuclear medicine technicians and the linens |
| were retrieved from the linen company.   There was no spread of              |
| contamination.                                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37341       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD                REGION:  4  |NOTIFICATION DATE: 09/18/2000|
|    UNIT:  [3] [] []                 STATE:  LA |NOTIFICATION TIME: 13:41[EDT]|
|   RXTYPE: [3] CE                               |EVENT DATE:        09/18/2000|
+------------------------------------------------+EVENT TIME:        11:50[CDT]|
| NRC NOTIFIED BY:  OSCAR PIPKINS                |LAST UPDATE DATE:  09/18/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JEFF SHACKELFORD     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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT OUTSIDE DESIGN BASIS OF FIRE PROTECTION PROGRAM                         |
|                                                                              |
| "During review of the plant Cable and Conduit List (CCL) database, it was    |
| observed that six essential cables were not listed as requiring fire wrap    |
| and the cables are not wrapped in the field. The cable, with one exception,  |
| is listed in the safe shutdown analysis as required for hot and cold safe    |
| shutdown, but are not provided with Appendix R separation per 10CFR50        |
| Appendix R Section IIIG. The cables are located in Room 299 on the +46 ft    |
| elevation of the Reactor Auxiliary Bldg (RAB) in Fire Area RAB 2. The        |
| condition has existed since plant original construction. At the time of      |
| discovery, the plant is operating at 100% Reactor Power. The cables were     |
| immediately listed as impaired, and compensatory actions were established    |
| (hourly fire watches). The condition has been entered into the plant         |
| corrective action program (CR-WF3-2000-1088). The equipment would be         |
| affected by a hypothetical fire in that fire area include the A/B Essential  |
| Chillers, RAB HVAG Exhaust Fan A, RAB HVAC Equipment Room Supply Fan AH-13   |
| (3A-SA) Dampers. These components should be the protected components in the  |
| fire area. The condition affects the ability to achieve safe shutdown.       |
| Therefore, the condition is considered to be outside the design basis of the |
| fire protection program."                                                    |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37342       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 09/18/2000|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 15:26[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        09/18/2000|
+------------------------------------------------+EVENT TIME:        14:15[CDT]|
| NRC NOTIFIED BY:  CARL EHRHARDT                |LAST UPDATE DATE:  09/18/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JEFF SHACKELFORD     R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       13       Power Operation  |13       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MAIN GENERATOR PARTIAL LOAD REJECT MAY NOT CAUSE REACTOR SCRAM AS ASSUMED    |
|                                                                              |
| "During evaluation of the data from a recent Reactor scram (Event #37325 on  |
| 9/15/00) a possible unanalyzed condition was found. Specifically, a Main     |
| Generator partial Load Reject can actuate a circuit contained in the turbine |
| controls that may not always activate a reactor scram/recirculation pump     |
| down shift as required by analysis. Theoretically, with the partial load     |
| reject that fails to actuate the Reactor Scram/Recirculation pump trip and   |
| assuming failure of the bypass valves, MCPR limits could be affected.        |
| Immediate corrective action is to change the setpoint of the EHC trip to     |
| ensure that a partial load reject will result in a scram and Recirculation   |
| pump transfer to slow speed."                                                |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37343       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE               REGION:  4  |NOTIFICATION DATE: 09/18/2000|
|    UNIT:  [] [2] []                 STATE:  CA |NOTIFICATION TIME: 15:55[EDT]|
|   RXTYPE: [1] W-3-LP,[2] CE,[3] CE             |EVENT DATE:        09/17/2000|
+------------------------------------------------+EVENT TIME:        06:20[PDT]|
| NRC NOTIFIED BY:  HOWARD SMITH                 |LAST UPDATE DATE:  09/18/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JEFF SHACKELFORD     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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OPERATORS MANUALLY STARTED EMERGENCY CONTAINMENT AIR COOLERS                 |
|                                                                              |
| "On  September 17, 2000, at about 0620 PDT, 2-ME-201 (non-safety containment |
| normal chiller) tripped on low oil  pressure. Operators began to start the   |
| containment normal chiller 2-ME-202, but stopped when prestart checks        |
| indicated low freon level. Because containment temperatures were slowly      |
| increasing, plant operators placed the emergency containment cooler units in |
| service and started an additional containment dome air circulator. To        |
| perform their ESF function, the containment emergency coolers automatically  |
| actuate on safety injection actuation signal and on containment pressure,    |
| but not on containment temperature. SCE considered that the emergency        |
| coolers were not performing an ESF function during this occurrence, and a    |
| report to the NRC was not required.                                          |
|                                                                              |
| "On September 18, 2000, at 1000 PDT, SCE determined that actuation of the    |
| emergency cooler units could be considered to meet the clarification         |
| provided in section 3.3.2 of NUREG-1022, Rev. 1. Therefore, SCE is           |
| conservatively and voluntarily providing this report to the NRC. After       |
| determining that 2-ME-202 was functional with an indicated low freon level,  |
| plant operators started 2-ME-202 at about 0818 PDT, terminating this         |
| occurrence. The emergency coolers and dome air circulators operated as       |
| designed. At the time of this occurrence, both units 2 and 3 were operating  |
| at about 100% power. Unit 1 remains permanently defueled."                   |
|                                                                              |
| The NRC resident inspector will be informed of this notification by the      |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37344       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 09/18/2000|
|    UNIT:  [] [2] []                 STATE:  MI |NOTIFICATION TIME: 19:51[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/18/2000|
+------------------------------------------------+EVENT TIME:        17:10[EDT]|
| NRC NOTIFIED BY:  SCOTT RICHARDSON             |LAST UPDATE DATE:  09/18/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ECCS PERFORMANCE POTENTIALLY IMPAIRED DUE TO VALVE CLOSURE DURING TESTING    |
|                                                                              |
| "During review of emergency core cooling system (ECCS) valve operability     |
| test procedures, it was determined that, on one occasion in 1995 and again   |
| in 1997, one safety injection (SI) system containment isolation valve (CIV)  |
| was closed for valve operability testing with reactor power at or near 100%. |
| With a CIV closed, injection from the two SI pumps following a small break   |
| loss of coolant accident (SBLOCA) would be directed to only two of the four  |
| reactor coolant system loops. At this power level, the high head SI system   |
| function of maintaining peak clad temperature (PCT) below 2200F following a |
| SBLOCA may not be satisfied. The condition becomes worse if a single failure |
| is considered to affect one of the two SI pumps. Further evaluation of the   |
| condition is in progress."                                                   |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37345       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2                    REGION:  4  |NOTIFICATION DATE: 09/18/2000|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 19:56[EDT]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        09/18/2000|
+------------------------------------------------+EVENT TIME:        15:09[PDT]|
| NRC NOTIFIED BY:  J. W. GASTON                 |LAST UPDATE DATE:  09/18/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JEFF SHACKELFORD     R4      |
|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     M/R        Y       65       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM DUE TO DECREASING CONDENSER VACUUM                      |
|                                                                              |
| "At 1425 PDT the plant experienced a sudden increase in offgas flow and      |
| decreasing condenser vacuum. Reactor power was reduced from 100% to 65% in   |
| accordance with the plant abnormal procedures for the loss of condenser      |
| vacuum. When the condenser back pressure continued to rise, a manual scram   |
| was inserted. All safety systems functioned as designed. The plant is        |
| currently stable in mode 3. The cause of the increase in off-gas flow is     |
| currently under investigation."                                              |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37346       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 09/19/2000|
|    UNIT:  [] [] [3]                 STATE:  IL |NOTIFICATION TIME: 01:26[EDT]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        09/18/2000|
+------------------------------------------------+EVENT TIME:        22:30[CDT]|
| NRC NOTIFIED BY:  BRIAN GRANT                  |LAST UPDATE DATE:  09/19/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          N       0        Refueling        |0        Refueling        |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DEGRADED WHILE SHUTDOWN - FAILED CONTAINMENT LEAK RATE TEST                  |
|                                                                              |
| System Engineering reports the local leak rate test results for 3A Feedwater |
| Header Inboard and  Outboard Drywell Check Valves (3-0220-58A & 3-0220-62A)  |
| are indeterminate due to excessive leakage. This exceeds the containment     |
| pathway leakage values allowed by Technical Specifications Primary           |
| Containment Leakage Rate Testing Program.                                    |
|                                                                              |
| The licensee will notify the NRC resident inspector.                         |
+------------------------------------------------------------------------------+