The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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 2200�F 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.                         |
+------------------------------------------------------------------------------+


Page Last Reviewed/Updated Wednesday, March 24, 2021