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Event Notification Report for September 18, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/15/2000 - 09/18/2000

                              ** EVENT NUMBERS **

37254  37324  37325  37326  37327  37328  37329  37330  37331  37332  37333  37334 
37335  37336  37337  37338  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37254       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 08/24/2000|
|    UNIT:  [1] [2] []                STATE:  NJ |NOTIFICATION TIME: 21:22[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        08/24/2000|
+------------------------------------------------+EVENT TIME:        20:30[EDT]|
| NRC NOTIFIED BY:  VAN FORD                     |LAST UPDATE DATE:  09/15/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHRISTOPHER CAHILL   R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONTROL ROOM VENTILATION NOT ALIGNED PROPERLY FOR TOXIC CHEMICAL DELIVERY    |
|                                                                              |
| The licensee reported that they were potentially outside of design license   |
| basis for the receipt of hazardous/toxic chemicals, specifically ammonium    |
| hydroxide 15 % by weight.  A delivery truck arrived at the site and was      |
| admitted to the protected area before the proper alignment was made for      |
| receipt.  The control room was contacted, but the alignment of control room  |
| ventilation was not completed prior to admitting the truck.  The control     |
| room ventilation has been placed in full recirculation for chemical receipt  |
| at this time.  The total time ventilation was not properly aligned is not    |
| available at this time.                                                      |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
|                                                                              |
| * * * UPDATE AT 2345 EDT ON 8/24/00 BY VAN FORD TO FANGIE JONES * * *        |
|                                                                              |
| The licensee reported there were no spills or discharges during the          |
| offloading process and there was no risk to onsite or offsite personnel at   |
| any time.  The chemical unloading procedure contains all requirements for    |
| personal protective equipment and appropriate precautions.  The chemistry    |
| department procedure for chemical delivery may be in conflict with Salem     |
| UFSAR requirements (Section 2.2.3.3), Hazardous Chemicals - Offsite.         |
| Station personnel are evaluating the issue.                                  |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.  The NRC          |
| Operations Officer notified the R1DO (Christopher Cahill).                   |
|                                                                              |
| * * * RETRACTION AT 1412 ET ON 09/15/00 BY FRANK SOENS TO JOHN MACKINNON * * |
| *                                                                            |
|                                                                              |
| An assessment of the consequences of a postulated failure of the ammonia     |
| tanker with the control room ventilation system being in its normal mode of  |
| operation results in a maximum Salem control room concentration of           |
| approximately 2.11 ppm which is less than the 100 ppm limit of Reg Guide     |
| 1.78.  Salem was within the design basis for the given situation, therefore, |
| this event is being retracted.  R1DO (Jim Trapp) notified.                   |
|                                                                              |
| The NRC Resident Inspector was notified of this event retraction by the      |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37324       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 09/15/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 01:40[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        09/14/2000|
+------------------------------------------------+EVENT TIME:        23:33[EDT]|
| NRC NOTIFIED BY:  KERRY ALLEN                  |LAST UPDATE DATE:  09/15/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES TRAPP          R1      |
|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                                   
+------------------------------------------------------------------------------+
| PRIMARY CONTAINMENT ISOLATION LOGIC RELAY COIL FAILED CAUSING SOME           |
| ISOLATIONS                                                                   |
|                                                                              |
| The primary containment isolation logic relay 16A-K61 coil apparently burned |
| out causing the relay to de-energize.  This caused valves 20 MOV-94 (DW      |
| equipment sump pump inboard isolation), 20 MOV-82 (DW floor sump pump        |
| inboard isolation), and 10 MOV-18 (RHR shutdown cooling inboard isolation)   |
| to receive a close signal. 20 MOV-94 and -82 went closed while 10 MOV-18 was |
| already closed.  The drywell sumps can not be pumped down.  This places the  |
| plant in the coolant leakage monitoring per technical specification 3.6.d    |
| which allows 24 hours for repair of the problem.  The problem is being       |
| worked on and investigated and it is expected to be completed within the 24  |
| hour limit.                                                                  |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37325       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 09/15/2000|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 10:27[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        09/15/2000|
+------------------------------------------------+EVENT TIME:        06:30[CDT]|
| NRC NOTIFIED BY:  DAVID HANKS                  |LAST UPDATE DATE:  09/15/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SANBORN         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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM DUE TO ELECTRICAL GRID DISTURBANCE                   |
|                                                                              |
| A Baxter Wilson Station 500 kV breaker opened inducing a grid disturbance    |
| that caused a reactor scram for an unknown reason.  The breaker opening      |
| cause a loss of one offsite source.  The disturbance also was picked up as   |
| an undervoltage on bus 15, which caused the division 3 (high pressure core   |
| spray) diesel generator to start.  The bus 16, which is fed from the same    |
| engineered safeguards features transformer, did not pick up the undervoltage |
| condition.  The reactor core isolation cooling system started and injected.  |
| The licensee is investigating the actual cause of the reactor scram.         |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   37326       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  KANSAS CITY RESEARCH MEDICAL CENTER  |NOTIFICATION DATE: 09/15/2000|
|LICENSEE:  KANSAS CITY RESEARCH MEDICAL CENTER  |NOTIFICATION TIME: 10:36[EDT]|
|    CITY:  KANSAS CITY              REGION:  3  |EVENT DATE:        08/30/2000|
|  COUNTY:                            STATE:  MO |EVENT TIME:             [CDT]|
|LICENSE#:  2418625-01            AGREEMENT:  N  |LAST UPDATE DATE:  09/15/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MIKE JORDAN          R3      |
|                                                |FREDRICK STURTZ      NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  EDMUND CYTACKI               |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF ONE I-125 SEED, 0.55 mCi                                             |
|                                                                              |
| The licensee discovered 1 of 65 iodine-125 seeds missing when installing     |
| them in an applicator for a permanent implant on 8/17/00.  Multiple surveys  |
| failed to find the seed if present in the shipment.  The shipment was        |
| received on 8/15/00 and surveyed, but not opened until the applicator was    |
| ready to be loaded.  The licensee contacted the manufacturer, Uramed         |
| Company, of Norwood, MA about the missing seed.  The manufacturer could not  |
| determine that they had not sent 65 seeds.  The seed is considered lost,     |
| probably in the hot lab of the hospital, and the licensee does not consider  |
| it to be a serious health risk.                                              |
|                                                                              |
| A written report will be submitted to the NRC.                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37327       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 09/15/2000|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 10:38[EDT]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        09/14/2000|
+------------------------------------------------+EVENT TIME:        18:30[EDT]|
| NRC NOTIFIED BY:  BRIAN TAYLOR                 |LAST UPDATE DATE:  09/15/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |STEPHEN CAHILL       R2      |
|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        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ERROR IDENTIFIED IN LOCA MODEL THAT COULD RESULT IN PEAK CLAD TEMPERATURE >  |
| 2200F                                                                       |
|                                                                              |
| "At 1830 hours on September 14, 2000, a condition potentially outside the    |
| design basis of the facility was identified at CR-3. This event notification |
| is being made as required by 10 CFR 50.46 for an error identified in the     |
| Evaluation Model for CR-3 which may result in peak clad temperature in       |
| excess of 2200F. This notification is being made while the unit is shutdown |
| prior to entry into MODE 2 following a recent maintenance outage.            |
|                                                                              |
| "The condition is that, in the event of a small break loss of coolant        |
| accident involving the core flood line at CR-3, it may be necessary to shut  |
| down the CR-3 reactor coolant pumps within 1 minute of loss of subcooling    |
| margin in order to limit peak cladding temperatures to less than 2200        |
| degrees Fahrenheit (the 10 CFR 50.46 limit for peak cladding temperatures).  |
| The current licensing/design basis analysis assumes that the pumps are shut  |
| down within 2 minutes of loss of subcooling margin.                          |
|                                                                              |
| "Existing procedural guidance in Emergency Operating Procedure requires      |
| turning off the reactor coolant pumps as an immediate manual action in       |
| response to loss of subcooling margin. Operator actions to trip the reactor  |
| coolant pumps are routinely monitored in training. Thc action to turn off    |
| the reactor coolant pumps upon loss of subcooling margin is routinely        |
| completed within 1 minute in plant simulator accident training unannounced   |
| casualty scenarios.                                                          |
|                                                                              |
| "Plant personnel for CR-3 have determined that, based upon the existing      |
| procedural guidance and simulator training experience, there is reasonable   |
| expectation that procedurally directed operator actions will successfully    |
| shut down the reactor coolant pumps within 1 minute of loss of subcooling    |
| margin and therefore, the peak cladding temperature will remain unchanged    |
| and below the 2200 degrees Fahrenheit limit of 10 CFR 50.46. Thus, the CR-3  |
| emergency core cooling systems continue to be operable because, based upon   |
| engineering judgement, the systems are capable of performing their intended  |
| safety function.                                                             |
|                                                                              |
| "This determination that a condition potentially outside the design basis of |
| the plant will be followed with more detailed evaluation and analysis of the |
| issue. It is possible that the-follow-up analysis-will provide technical     |
| justification which demonstrates that CR-3 remains within the existing       |
| design basis.                                                                |
|                                                                              |
| "CR-3 is reporting this prior to placing the plant in operation. This report |
| is being made under 10 CFR 50.72(b)(1)(ii)(B) as 'Any event or condition     |
| during operation that results in a condition that is outside the design      |
| basis of the plant.' CR-3 is currently in a shutdown condition in the        |
| process of performing a plant start-up. Therefore, the one-hour criteria of  |
| this reporting requirement is not in effect.                                 |
|                                                                              |
| "At its most fundamental level, PSC 2-00 identifies an analytical issue that |
| requires resolution. A telecon with NRC technical staff held on 9/13/2000    |
| identified the analytical issue as one that is principally concerned with an |
| ECCS evaluation model assumption. The safety significance was alleviated by  |
| discussions on consistent, demonstrated performance of immediate operator    |
| action to trip the RCPs well within 1 minute, with no challenge to the       |
| preliminary (conservative) accident analysis. Additionally, discussions were |
| also presented on the relative probability of this specific scenario. The    |
| combination of the break with the specific failure represents a very small   |
| probability (<E-10), which helps diminish the safety significance of this    |
| scenario.                                                                    |
|                                                                              |
| "CR3 is proceeding with an approach that conservatively addresses Mode 2     |
| restraint because decay heat power is low at this time since the reactor is  |
| shutdown and will not increase significantly until further power operation   |
| is commenced."                                                               |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37328       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WA DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 09/15/2000|
|LICENSEE:  WASHINGTON STATE UNIVERSITY          |NOTIFICATION TIME: 15:38[EDT]|
|    CITY:  PULLMAN                  REGION:  4  |EVENT DATE:        09/01/2000|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PDT]|
|LICENSE#:  WA-C003-1             AGREEMENT:  Y  |LAST UPDATE DATE:  09/15/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SANBORN         R4      |
|                                                |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TERRY FRAZEE                 |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LEAKING SOURCE, SODIUM-22, DISCOVERED DURING LEAK TEST.                      |
|                                                                              |
| THE FOLLOWING EVENT WAS EVENT WAS E-MAILED TO THE HEADQUARTERS OPERATION     |
| CENTER                                                                       |
|                                                                              |
| Washington State University located in Pullman, WA Radiation Safety Officer  |
| performed a leak test on a 1.5 millicurie sodium-22 source that was planned  |
| to be transferred from one authorized user to another.  The source was found |
| to be leaking and will be disposed.  Surveys of the storage area and work    |
| area were done and decontamination performed on the remote handling tools.   |
| The source is one of four custom made by a researcher at Brookhaven National |
| Lab in June 1996 and transferred to Washington State University (WSU) when   |
| the researcher moved to WSU.  Of the four sources, one was found to be       |
| leaking and disposed of several years ago, one is still at WSU, and the last |
| was transferred to another academic institution (WSU has notified the        |
| recipient of this event).                                                    |
|                                                                              |
| Leak test?  0.027 microcuries of removable contamination detected.           |
|                                                                              |
| Activity and isotope involved:  1.5 millicuries of Na-22 as of June 1996.    |
|                                                                              |
| Washington State event report:  WA-00-044.                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37329       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 09/15/2000|
|LICENSEE:  AGILENT TECHNOLOGIES, INC.           |NOTIFICATION TIME: 17:04[EDT]|
|    CITY:  NEWARK                   REGION:  4  |EVENT DATE:        08/15/2000|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  09/15/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SANBORN         R4      |
|                                                |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KENT PRENDERGAST             |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 187 MICROCURIE PROMETHIUM-147 SOURCE LOST                                    |
|                                                                              |
| Promethium-147 is held under a General License. State of California event #  |
| CA-09-15-00                                                                  |
|                                                                              |
| Agilent Technologies, Inc. located in Newark, CA was preparing to ship a 187 |
| microcurie Promethium-147 source back to Hewlett Packard located in San      |
| Jose, CA.   The source was taken out of its container and placed on a desk   |
| in a cubicle located in an Agilent Technology, Inc. building.  When the      |
| person came back to get the source it was missing. Employees in the area     |
| were asked if they had seen or taken the small source and a survey of the    |
| area was performed to find the source.  The source was not found.  The       |
| original activity of the source, November 1994, was 900 microcuries.  The    |
| half life of Promethium-147 is 2.62 years.  The missing Promethium-147 was   |
| used in a Betascope which is used  to measure the thickness of silicon       |
| wafers.                                                                      |
|                                                                              |
| Agilent Technologies, Inc. notified the State of California regarding the    |
| missing source on 08/17/00                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37330       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 09/15/2000|
|    UNIT:  [2] [] []                 STATE:  PA |NOTIFICATION TIME: 17:57[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        09/15/2000|
+------------------------------------------------+EVENT TIME:        15:05[EDT]|
| NRC NOTIFIED BY:  JESSE JAMES                  |LAST UPDATE DATE:  09/15/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES TRAPP          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       15       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUALLY SCRAMMED THE REACTOR AFTER ENTERING THE RESTRICTIVE AREA OF THE     |
| POWER TO FLOW MAP.                                                           |
|                                                                              |
| On September 15, 2000 at Peach Bottom Atomic Power Station, Unit 2 was       |
| manually scrammed per operating procedure during turbine testing in          |
| preparation for the refuel outage.                                           |
|                                                                              |
| The manual scram was due to entering restricted area of the power to flow    |
| map from Technical Specification 3.4.1, after the trip of the "2B"           |
| recirculation pump.  All rods fully inserted and the reactor was shutdown.   |
| Reactor level during the scram lowered to 0" and a Group II and III primary  |
| and secondary containment isolation was received.  The isolations functioned |
| as designed.  The plant is stable in hot shutdown with the main condenser as |
| a heat sink and the feedwater system is in service for level control.  No    |
| radioactive release or Emergency Core Cooling System injection occurred      |
| during the scram.                                                            |
|                                                                              |
| The turbine was tripped in accordance with the refuel outage plan when the   |
| recirculation pump tripped.  The plan was to perform turbine testing and     |
| then to manually scram the reactor at the same power level.                  |
|                                                                              |
| The reactor was manually scrammed less than one minute after entering the    |
| restricted area of the power to flow map.  No power oscillations were seen.  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37331       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WA DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 09/15/2000|
|LICENSEE:  TRANSALTA CENTRALIA MINING LLC       |NOTIFICATION TIME: 19:32[EDT]|
|    CITY:  CENTRALIA                REGION:  4  |EVENT DATE:        09/13/2000|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PDT]|
|LICENSE#:  WN-I0241-1            AGREEMENT:  Y  |LAST UPDATE DATE:  09/15/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SANBORN         R4      |
|                                                |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TERRY FRAZEE                 |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MECHANICAL FAILURE OF A RONAN MODEL SA-4 GAUGING DEVICE                      |
|                                                                              |
| THE FOLLOWING EVENT WAS E-MAILED TO THE HEADQUARTERS OPERATION CENTER        |
|                                                                              |
| Transalta Centralia Mining LLC notified the WA Department of Health,         |
| Division of Radiation Protection, of a mechanical failure involving a Ronan  |
| Engineering Company Model SA-4 gauging device.  The device is specifically   |
| licensed for density process measurements and uses a Cesium-137 sealed       |
| source, Amersham Model CDC.711M not to exceed 74 gigabecquerels (2 curies).  |
| The source is normally mounted at the end of a source rod and secured by     |
| pins.  When not in operation, the rod with source can be withdrawn into a    |
| safe position inside the shielding device.  When operating, the rod with     |
| source is inserted into the process area through a dry well.  An authorized  |
| user realized that a problem existed when attempting to return the source to |
| the safe position.  Apparently the rod did not have normal feel when it was  |
| withdrawn.  The licensee's RSO and their health physics consultant surveyed  |
| the area and stated there wasn't a dose rate problem since the process       |
| mixture was still providing ample shielding.  The mixture will remain        |
| in-place until the source can be returned to the device's normal shielded    |
| position.  The area adjacent to the dry-well access point has been marked as |
| a restricted area.                                                           |
|                                                                              |
| Preliminary indications are the source has separated from the source rod and |
| fallen to the bottom of the insertion well.  The consultant indicated that   |
| this type Ronan device (but not this particular device) has suffered similar |
| failures in the past.                                                        |
|                                                                              |
| The consultant has contacted Ronan Engineering requesting they send          |
| procedures and special equipment.  The recovery operation is anticipated to  |
| take place on September 18.  The Department of Health, Division of Radiation |
| Protection will be on-site during the recovery operation.                    |
|                                                                              |
| Type of License:  Fixed Gauge                                                |
|                                                                              |
| Washington Event Report: WA-00-046.                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37332       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES                REGION:  3  |NOTIFICATION DATE: 09/15/2000|
|    UNIT:  [1] [] []                 STATE:  MI |NOTIFICATION TIME: 23:47[EDT]|
|   RXTYPE: [1] CE                               |EVENT DATE:        09/15/2000|
+------------------------------------------------+EVENT TIME:        23:25[EDT]|
| NRC NOTIFIED BY:  M MLYNARBK                   |LAST UPDATE DATE:  09/16/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |MARK RING            R3      |
|10 CFR SECTION:                                 |JOHN ZWOLINSKI       NRR     |
|AAEC                                            |FRANK CONGEL         IRO     |
|                                                |DAN SULLIVAN         FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT - UNIDENTIFIED LEAKAGE GREATER THAN 1GPM                       |
|                                                                              |
| The plant is in hot shutdown making preparations for startup.  Reactor       |
| coolant is back leaking from loop "1A" through two check valves into a       |
| safety injection tank.  The safety injection tank is approximately 95% full. |
| If the tank should over pressurize the relief valve will relieve to the      |
| containment.  The primary containment integrity is set.  The maximum leak    |
| rate observed was 1.64 GPM.  The licensee has taken steps to seat the check  |
| valves and is now measuring the leak rate again.  The unusual event was      |
| declared at 2325.                                                            |
|                                                                              |
| The licensee notified the NRC resident inspector, the state and Van Buren    |
| county.                                                                      |
|                                                                              |
| * * * UPDATE AT 0145 ON 9/16/00 BY SLEEPER, RECEIVED BY WEAVER * * *         |
|                                                                              |
| The licensee terminated the unusual event at 0121.  Unidentified leakage has |
| returned to its normal value of less than 1 GPM.  The licensee will notify   |
| the NRC resident inspector.  The Operations center notified the RDO (RING);  |
| NRR EO (ZWOLINSKI); IRO (CONGEL) and FEMA (CEGIELSKI).                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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:   37334       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE                   REGION:  2  |NOTIFICATION DATE: 09/17/2000|
|    UNIT:  [1] [] []                 STATE:  GA |NOTIFICATION TIME: 11:03[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/17/2000|
+------------------------------------------------+EVENT TIME:        08:09[EDT]|
| NRC NOTIFIED BY:  WILLIAM DUNN                 |LAST UPDATE DATE:  09/17/2000|
|  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        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BRIEF ENTRY INTO TECHNICAL SPECIFICATION 3.0.3                               |
|                                                                              |
| "During attempts to restore Train 'A' Safety Injection (SI) system following |
| planned testing, the Train 'B' SI system was rendered inoperable for 1       |
| minute requiring entry in TS 3.0.3. The high and low head injection systems  |
| were operable.                                                               |
|                                                                              |
| "Train 'A' SI was inoperable due to planned RCS pressure isolation valve     |
| inservice testing.  During the Train 'A' SI testing, valve 1HV-8802A (SI-PMP |
| A TO HOT LEG 1&4 ISO VLV) had to be manually closed.   In order to return    |
| Train 'A' SI to service, 1HV-8802A would have to be manually unseated and    |
| then electrically stroked.  The Train 'A' SI pump was placed in PTL          |
| [pull-to-lock] to ensure that the SI pump would not run out should the SI    |
| pump auto start.  The control room staff, however did not recognize the      |
| impact on Train 'B' SI, during stroke of 1HV-8802A with the SIP TO COLD LEG  |
| isolation valves (1HV-8821 A&B) open.  In this configuration, the potential  |
| existed to run out the Train 'B' SI pump should the pump auto start.  The    |
| control staff within a few minutes of stroking 1 HV-8802A recognized the     |
| entry into TS 3.0.3."                                                        |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37335       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 09/17/2000|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 16:33[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        09/17/2000|
+------------------------------------------------+EVENT TIME:        15:20[EDT]|
| NRC NOTIFIED BY:  GREGG R. PITTS               |LAST UPDATE DATE:  09/17/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       70       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNEXPECTED MAIN TURBINE TRIP CAUSED AN AUTOMATIC REACTOR SCRAM.              |
|                                                                              |
| During power ascension following a planned outage, Nine Mile Point Unit 2    |
| automatically scrammed from approximately 70% reactor power.  The scram      |
| signal was generated when the Main Turbine tripped.  The cause of the        |
| Turbine Trip is being investigated.  All control rods fully inserted.        |
| Reactor pressure is stable and being controlled through Turbine Bypass       |
| Valves to the Main Condenser.  One additional scram signal was received on   |
| low Reactor Vessel Water Level during level recovery efforts.  Reactor level |
| control is stable and being fed from the condensate/feedwater system.  All   |
| Emergency Core Cooling Systems are operable and in standby.                  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37336       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD                REGION:  3  |NOTIFICATION DATE: 09/17/2000|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 17:45[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/17/2000|
+------------------------------------------------+EVENT TIME:        06:46[CDT]|
| NRC NOTIFIED BY:  RANDY MAU                    |LAST UPDATE DATE:  09/17/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK RING            R3      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| A licensee employee in the protected area was found with a metal flask       |
| containing a small amount of alcohol, approximately one teaspoon or less.    |
| It was later determined that the individual was unaware that the flask was   |
| in his coat pocket.  The individual was escorted offsite.  A behavior        |
| observation was performed, and the individual was allowed to return to work. |
|                                                                              |
|                                                                              |
| The NRC Resident will be notified of this event by the licensee.             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37337       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  IDAHO NAT ENGR & ENVIRONMENTAL LAB   |NOTIFICATION DATE: 09/17/2000|
|LICENSEE:  IDAHO NAT ENGR & ENVIRONMENTAL LAB   |NOTIFICATION TIME: 19:07[EDT]|
|    CITY:  IDAHO FALLS              REGION:  4  |EVENT DATE:        09/17/2000|
|  COUNTY:                            STATE:  ID |EVENT TIME:        16:47[MDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  09/17/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SANBORN         R4      |
|                                                |ELLIS MERSCHOFF      RA      |
+------------------------------------------------+LARRY CAMPER         NMSS    |
| NRC NOTIFIED BY:  JOE GARCIA                   |FRANK CONGEL         IRO     |
|  HQ OPS OFFICER:  JOHN MacKINNON               |DAN SULLIVAN         FEMA    |
+------------------------------------------------+ROBERT CONLEY        USDA    |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| COURTESY NOTIFICATION OF A DOE EMERGENCY DECLARATION AT AN INDEPENDENT SPENT |
| FUEL STORAGE INSTALLATION (ISFSI) IN IDAHO.                                  |
|                                                                              |
| At 1647MDT, DOE INEEL declared a Site Area Emergency due to wildland fires   |
| on DOE controlled property,  2 miles North East of INTEC.  The ISFSI         |
| containing the TMI spent fuel is not threatened.  This notification is a     |
| courtesy call only and does not involve the NRC Radiological Emergency Plan. |
| No NRC assistance is requested.                                              |
|                                                                              |
| DOE INEEL has notified the State of Idaho, all surrounding counties and DOE  |
| Headquarters.                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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.                            |
+------------------------------------------------------------------------------+