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Event Notification Report for February 20, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/16/2001 - 02/20/2001

                              ** EVENT NUMBERS **

37630  37694  37735  37749  37753  37754  37755  37756  37757  37758  37759  37760 
37761  37762  37763  37764  37765  37766  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37630       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 12/22/2000|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 11:29[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        12/22/2000|
+------------------------------------------------+EVENT TIME:        09:45[CST]|
| NRC NOTIFIED BY:  RICK HUBBARD                 |LAST UPDATE DATE:  02/19/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BILL JONES           R4      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| LOSS OF POWER TO THE TECHNICAL SUPPORT CENTER (TSC)                          |
|                                                                              |
| Breaker 13-40 tripped with the ground flag dropped.  This breaker supplies   |
| primary power to the TSC.  There is a backup diesel generator available to   |
| supply power to the TSC but will not be energized until it is determined     |
| that there is no ground at the TSC.  Once the TSC D/G is energized the       |
| facility will once again be available.                                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * Update at 1150 on 12/22/00 by Hubbard received by Weaver * * *         |
|                                                                              |
| The diesel generator is now supplying the TSC with electrical power (as of   |
| 1041 CST).  Investigation continues into why breaker 13-40 tripped.          |
|                                                                              |
| Notified the R4DO(Jones).                                                    |
|                                                                              |
| * * * RETRACTED AT 1309 EST ON 2/19/01 BY CHRIS REEKIE TO FANGIE JONES * *   |
| *                                                                            |
|                                                                              |
| The licensee is retracting this event. Upon review of the potential loss of  |
| emergency communications and assessment capability they have determined that |
| no such loss would have happened with the initial problem.                   |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R4DO (Greg Pick) has  |
| been notified.                                                               |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   37694       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WAUSAU HOSPITAL                      |NOTIFICATION DATE: 01/26/2001|
|LICENSEE:  WAUSAU HOSPITAL                      |NOTIFICATION TIME: 11:36[EST]|
|    CITY:  WAUSAU                   REGION:  3  |EVENT DATE:        01/24/2001|
|  COUNTY:                            STATE:  WI |EVENT TIME:        07:30[CST]|
|LICENSE#:  48-01032-01           AGREEMENT:  N  |LAST UPDATE DATE:  02/16/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JAMES CREED          R3      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JEFF LIMMER                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION                                                    |
|                                                                              |
| A Cs-137 vaginal cylinder implant was loaded at 9:30 am on 1/23/01.  The     |
| written directive called for a total implant time of 49 hours.  During a     |
| check of the patient at 7:30 am on 1/24/01, the authorized user found the    |
| loaded vaginal cylinder on the patient's toilet seat.  The patient's nurse   |
| stated that the source came out at about 6:30 am on 1/24/01 (i.e., after     |
| about 42% of the prescribed dose was delivered).  The licensee was not sure  |
| how the source got to where it was found.  The authorized user placed the    |
| cylinder in a lead pig and transported it to the secured storage area.  The  |
| authorized user decided to write another written directive and reload the    |
| patient at 10:00 am on 1/24/01 with a prescribed implant time of 7 hours.    |
| After the 7 hours, the sources were explanted as intended.  The authorized   |
| user decided to deliver the remaining radiation dose to the treatment site   |
| via teletherapy.                                                             |
|                                                                              |
| At 6:00 am on 1/24/01, the nurse emptied the patient's foley bag and noted   |
| that the patient was in bed.  Between 6:00 and 6:30 am on 1/24/01, the nurse |
| noticed that the patient was leaving the bathroom to go back to bed.  The    |
| nurse also noticed that the patient's "T-binder" (used to hold the           |
| applicator in place), was loose, so she tightened it.  The authorized user   |
| visited the patient at 7:30 am and noticed that the T-binder was on the      |
| bathroom floor and the loaded vaginal cylinder was on the toilet seat.       |
| Based on nurse interviews, all nurses caring for the patient were badged,    |
| and none of them handled the applicator.                                     |
|                                                                              |
| ***** UPDATE/RETRACTION AT 1043 EST ON 02/16/01 FROM JEFF LIMMER TO LEIGH    |
| TROCINE *****                                                                |
|                                                                              |
| An investigation was performed, and the NRC Region 3 office (Tony Go and     |
| Geoffrey Wright) notified the license that there was patient intervention.   |
| Therefore, the licensee is retracting this event.                            |
|                                                                              |
| The NRC operations officer notified the R3DO (Monte Phillips) and NMSS EO    |
| (Brian Smith).                                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37735       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  STANDARD TESTING AND ENGINEERING CO  |NOTIFICATION DATE: 02/11/2001|
|LICENSEE:  STANDARD TESTING AND ENGINEERING CO  |NOTIFICATION TIME: 19:11[EST]|
|    CITY:  DEL CITY                 REGION:  4  |EVENT DATE:        02/10/2001|
|  COUNTY:                            STATE:  OK |EVENT TIME:             [CST]|
|LICENSE#:  35-17054-01           AGREEMENT:  Y  |LAST UPDATE DATE:  02/17/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SANBORN         R4      |
|                                                |PHILIP TING          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HURST                        |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STOLEN TROXLER GAUGE                                                         |
|                                                                              |
| A Troxler 3430 serial #16299 was stolen out of the back of an employee's     |
| truck while it was parked at his house in Del City(a suburb of Oklahoma      |
| City).  The gauge, which contained 8 millicuries Cs-137 and 40 millicuries   |
| Am-241/Br, was triple locked in the back of the truck.  It was stolen on the |
| night of 2/10/01 or the morning of 2/11/01.  The local police were notified. |
| Troxler was notified and they will notify the state.                         |
|                                                                              |
| * * * UPDATE 1409 2/17/2001 FROM HURST TAKEN BY STRANSKY * * *               |
|                                                                              |
| The gauge was recovered earlier today. It was found intact in its case. The  |
| licensee is currently performing a wipe test of the device to be sure that   |
| there was no leakage.                                                        |
|                                                                              |
| Notified R4DO(Pick).                                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37749       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 02/14/2001|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 17:05[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        02/14/2001|
+------------------------------------------------+EVENT TIME:        08:51[CST]|
| NRC NOTIFIED BY:  BRUCE SCHOENBACH             |LAST UPDATE DATE:  02/16/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GREG PICK            R4      |
|10 CFR SECTION:                                 |                             |
|*IND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| BOTH TRAINS OF CONTAINMENT COOLERS AND ONE TRAIN OF CONTAINMENT SPRAY        |
| INOPERABLE                                                                   |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On 2/14/01, the 'A' train containment cooling train was removed from        |
| service at 0507 CST for associated circuit breaker work. At 0851 CST the 'B' |
| Train Essential Service Water pump was started to support performance of the |
| 'A' Train SIS/CIS Slave Relay Test.                                          |
|                                                                              |
| "The 'B' Essential Service Water pump failed to achieve rated flow and       |
| pressure and was declared inoperable at 0851 CST. This resulted in entry     |
| into Technical Specification LCO 3.6.6, Required Action F.1 for both trains  |
| of containment coolers inoperable and one train ('B') of Containment Spray   |
| inoperable. LCO 3.6.6 Required Action F.1 also requires entry into LCO       |
| 3.0.3. Technical Specification 3.0.3 was entered at 0851 CST and exited at   |
| 1123 CST when the 'A' train of Containment Cooling was returned to service.  |
| The plant remains in Technical Specification LCO 3.7.8 Required Action A.1   |
| (72-Hour Action Statement) for one train ('B') of Essential Service Water    |
| inoperable.                                                                  |
|                                                                              |
| "This condition at the time of discovery could have prevented the            |
| fulfillment of the safety function of structures or systems that are needed  |
| to control the release of radioactive material or mitigate the consequences  |
| for an accident. It was concluded that this event was reportable per         |
| 10CFR50.72(b) (3) (v) since:                                                 |
|                                                                              |
| (1) Both trains of containment cooling were lost as a result of the          |
| unanticipated failure of the 'B' train Essential Service Water pump in       |
| conjunction with the 'A' train containment coolers being removed from        |
| service.                                                                     |
| (2) Cascading through technical specification resulted in the loss of 'B'    |
| train containment spray system.                                              |
|                                                                              |
| "The failure of the 'B' train Essential Service Water pump is under          |
| evaluation."                                                                 |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| UPDATE 1706 2/15/2001 VIA FACSIMILE TO STRANSKY * * *                        |
|                                                                              |
| "Upon investigation of the 'B' Essential Service Water pump problem, an      |
| obstruction was found in the suction of the pump. The obstruction was        |
| subsequently removed and the pump was then started to evaluate the           |
| operability condition of 'B' Essential Service Water pump. The pump was      |
| evaluated for normal flow, discharge pressure, and vibration. All parameters |
| were found within normal operating limits, the 'B' Essential Service Water   |
| pump was declared Operable at 0231 on 2/15/O1 and Technical Specifications   |
| 3.7.8.A.1 and 3.8.1.B were exited."                                          |
|                                                                              |
| Notified R4DO (Pick).                                                        |
|                                                                              |
| *** UPDATE AT 0615 ON 02/16/01 - LEIGH TROCINE CALLED SITE (JOHN DAMPS) ***  |
|                                                                              |
| The obstruction was a 20-foot long piece of tygon tubing.  It was reported   |
| that the tubing had been hanging from a funnel near a hole in a pre-lube     |
| tank for the pump's seals.  Apparently, the tubing fell into a drain and     |
| made its way to the pump suction.                                            |
|                                                                              |
| The licensee stated that the resident inspectors were aware of this          |
| information.  The NRC operations center notified the R4DO (Pick).            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37753       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MARTIN MARIETTA ANDERSON CREEK QUAR  |NOTIFICATION DATE: 02/16/2001|
|LICENSEE:  UNKNOWN                              |NOTIFICATION TIME: 10:59[EST]|
|    CITY:  ROCKVILLE                REGION:  2  |EVENT DATE:        02/15/2001|
|  COUNTY:  GOOCHLAND                 STATE:  VA |EVENT TIME:             [EST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  02/16/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CLIFFORD ANDERSON    R1      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  BENJAMIN BROWN               |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TRANSPORT AND SUBSEQUENT DISCOVERY OF SCRAP METAL CONTAINING 50 MILLICURIES  |
| OF CESIUM-137 (NRC GENERALLY LICENSED MATERIAL) AT MARTIN MARIETTA ANDERSON  |
| CREEK QUARRY                                                                 |
|                                                                              |
| On 02/13/01, Martin Marietta Anderson Creek Quarry (located in Rockville,    |
| Virginia, near Richmond) shipped scrap metal to Cycle Systems (a scrap yard  |
| located in Lynchburg, Virginia).  Cycle Systems surveyed the material and    |
| discovered 50 millicuries of cesium-137.  (The material was apparently a     |
| sensor or level gauge from a conveyer system.)                               |
|                                                                              |
| Cycle Systems notified the quarry and the State of Virginia.  The State of   |
| Virginia notified the NRC Region 2 office, and the NRC Region 2 office (Wade |
| Loo) contacted the quarry.                                                   |
|                                                                              |
| The material was returned to the quarry on 02/15/01.  The shutter is         |
| currently locked closed, and the material has been placed in an office.      |
| Martin Marietta Anderson Creek Quarry believes that the material may have    |
| come from another quarry.  The actual source of the material is currently    |
| being investigated.                                                          |
|                                                                              |
| (Call the NRC Operations Center for quarry contact telephone number.)        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37754       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 02/16/2001|
|    UNIT:  [1] [2] []                STATE:  PA |NOTIFICATION TIME: 14:47[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        02/16/2001|
+------------------------------------------------+EVENT TIME:        08:15[EST]|
| NRC NOTIFIED BY:  GRANT FERNSLER               |LAST UPDATE DATE:  02/16/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLIFFORD ANDERSON    R1      |
|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                                   
+------------------------------------------------------------------------------+
| FITNESS FOR DUTY REPORT                                                      |
|                                                                              |
| A non-licensed employee tested positive for the use of illegal drugs during  |
| a random test. The test results were confirmed positive by the licensee      |
| Medical Review Officer. The individual's access to the plant has been        |
| suspended in accordance with the licensee's FFD program. The NRC resident    |
| inspector has been informed of this notification by the licensee.            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37755       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 02/16/2001|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 15:40[EST]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        02/16/2001|
+------------------------------------------------+EVENT TIME:        15:05[EST]|
| NRC NOTIFIED BY:  JIM HICKEY                   |LAST UPDATE DATE:  02/16/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANNE BOLAND          R2      |
|10 CFR SECTION:                                 |                             |
|*PRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO RECEIPT OF CONTAMINATED ITEMS                    |
|                                                                              |
| "While performing routine surveys, Turkey Point Health Physics personnel     |
| discovered low levels of radioactivity on several plastic Caution signs      |
| received from the Byron Nuclear Power Station. The signs were surveyed at    |
| Turkey Point prior to use in the site's radiation controlled area. These     |
| items were counted in a Small Articles Monitor (SAM) and indicated low level |
| contamination was present. In total, 6 out of approximately 650 items        |
| surveyed indicated the presence of low level fixed activity. The highest     |
| level measured was 7,000 disintegrations per minute (dpm) using a standard   |
| HP-210 (pancake GM) probe. Isotopic analysis indicates cobalt-60 and         |
| manganese-54. One item had low levels of loose surface contamination (57     |
| dpm/100 cm2). The items identified with low level fixed contamination are    |
| now being held inside the Turkey Point radiation controlled area. The signs  |
| were shipped in cardboard boxes and no loose surface contamination was found |
| on the exterior of the boxes                                                 |
|                                                                              |
| "Florida Power & Light Company has notified the Byron Station and the State  |
| of Florida (Department of Health, Bureau of Radiation Control) of this       |
| matter."                                                                     |
|                                                                              |
| The licensee has informed the NRC resident inspector of this notification.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37756       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 02/16/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 16:36[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/15/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        23:20[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  02/16/2001|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MONTE PHILLIPS       R3      |
|  DOCKET:  0707002                              |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| VALID ACTIVATION OF  SAFETY SYSTEM                                           |
|                                                                              |
| "At 2320 hours on 02/15/01, both the 'A' and 'B' High Level Condensate       |
| Alarms activated on Autoclave #2 in the X-343 Feed and Sampling Facility.    |
| The activation of either of these alarms will cause the autoclave steam      |
| supply valves ('Q' components) to actuate (close). The steam supply valves   |
| closed, as designed, upon the activation of the High Condensate Alarms,      |
| Autoclave #2 was in TSR Mode IV (FEEDING) at the time of the alarm           |
| activations. Operations personnel immediately responded to the alarms in     |
| accordance with the approved Alarm Response Procedures. Both alarms reset    |
| when the operations personnel acknowledged the alarms at the local autoclave |
| control panel. All autoclave (and cylinder) operating parameters were        |
| determined be to within normal ranges. Autoclave #2 was placed in TSR mode   |
| VII (Shutdown) by operations personnel and declared Inoperable by the Plant  |
| Shift Superintendent's Office. Based on the actuation of both High Level     |
| Condensate alarms, this event is being reported as a valid safety system     |
| actuation, a 24-hour NRC event."                                             |
|                                                                              |
| The NRC resident inspector has been informed of this event.                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37757       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 02/16/2001|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 19:41[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        02/16/2001|
+------------------------------------------------+EVENT TIME:        16:30[CST]|
| NRC NOTIFIED BY:  MARTY McADORY                |LAST UPDATE DATE:  02/16/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GREG PICK            R4      |
|10 CFR SECTION:                                 |                             |
|*IND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE SPRAY SYSTEM DECLARED INOPERABLE                          |
|                                                                              |
| "During performance of 1C3 battery all-cell checks, battery cell #38 was     |
| found to be >0.020 below the average for specific gravity. Tech Spec 3.8.6,  |
| 'Battery Cell Parameters,' requires declaring 1C3 battery inoperable. This   |
| caused entry into Tech Spec 3.8.4 Action D, which is to declare the High     |
| Pressure Core Spray system inoperable. This requires entry into a 14 day     |
| LCO. This event is reportable since High Pressure Core Spray is a single     |
| train system."                                                               |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37758       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 02/17/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 03:17[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/16/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        10:20[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  02/17/2001|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MONTE PHILLIPS       R3      |
|  DOCKET:  0707001                              |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TOM WHITE                    |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)        SAFETY EQUIPMENT FAILUR|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFETY EQUIPMENT FAILED TO FUNCTION AS REQUIRED BY TECHNICAL SAFETY          |
| REQUIREMENT                                                                  |
|                                                                              |
| "At 1020 on 02-16-01, the Plant Shift Superintendent (PSS) was notified of a |
| safety system failure in the C-315 building. While closing the cylinder      |
| valve on a full liquid cylinder, the valve failed to close completely when a |
| shear pin broke on the emergency cylinder valve closure mechanism.  At the   |
| time of the failure the cylinder valve was still approximately one eighth of |
| a turn open. The operator manually closed the valve thus placing the         |
| cylinder in a safe mode. The emergency cylinder valve closure mechanism is   |
| part of the Low Voltage UF6 Release Detection and Isolation System at the    |
| Withdrawal Stations, and is required to be operable according to TSR         |
| 2.3.4.1.                                                                     |
|                                                                              |
| "This event is reportable under 10 CFR 76.120(c)(2) as an event in which     |
| equipment required by the TSR is disabled or falls to function as designed.  |
|                                                                              |
| "The NRC Senior Resident has been notified of this event."                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37759       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 02/17/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 12:49[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/16/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        21:37[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  02/17/2001|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MONTE PHILLIPS       R3      |
|  DOCKET:  0707002                              |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| VALID ACTUATION OF SAFETY SYSTEM                                             |
|                                                                              |
| "At 2137 hours on 02/16/01, both the 'A' and 'B' High Level Condensate       |
| Alarms activated on Autoclave #1 in the X-343 Feed and Sampling Facility.    |
| The activation of either of these alarms will cause the autoclave steam      |
| supply valves ('Q' components) to actuate (close). The steam supply valves   |
| closed, as designed, upon the activation of the High Condensate Alarms.      |
| Autoclave #1 was in TSR Mode II (HEATING) at the time of the alarm           |
| activations. Operations personnel immediately responded to the alarms in     |
| accordance with the approved Alarm Response Procedures. Both alarms reset    |
| when the operations personnel acknowledged the alarms at the local autoclave |
| control panel. All autoclave (and cylinder) operating parameters were        |
| determined be to within normal ranges, Autoclave #1 was placed in TSR mode   |
| VII (Shutdown) by operations personnel and declared Inoperable by the Plant  |
| Shift Superintendent's Office. Based on the actuation of both High Level     |
| Condensate alarms, this event is being reported as a valid safety system     |
| actuation, a 24-hour NRC event. An Engineering Evaluation has been requested |
| to investigate the circumstances surrounding this safety system actuation."  |
|                                                                              |
| The NRC resident inspector has been informed of this event.                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37760       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 02/19/2001|
|    UNIT:  [] [] [3]                 STATE:  SC |NOTIFICATION TIME: 01:22[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        02/18/2001|
+------------------------------------------------+EVENT TIME:        21:00[EST]|
| NRC NOTIFIED BY:  LOUIS NOWELL                 |LAST UPDATE DATE:  02/19/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANNE BOLAND          R2      |
|10 CFR SECTION:                                 |JOHN ZWOLINSKI       NRR     |
|*UNA 50.72(b)(3)(ii)(B)  UNANALYZED COND OP     |NADER MAMISH         IRO     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| INDICATION OF PRESSURE BOUNDARY LEAKAGE DISCOVERED DURING VISUAL INSPECTION  |
| OF REACTOR VESSEL HEAD                                                       |
|                                                                              |
| "Event:  Preliminary Reactor Vessel Head visual inspection indicates a small |
| amount of boron residue surrounding 6 Control Rod Drive mechanism head       |
| penetrations.  These indications are similar to those previously reported    |
| during U-1 EOC-19 refueling outage.                                          |
|                                                                              |
| "Initial Safety Significance:  Preliminary indication of leakage through     |
| Reactor Coolant System Pressure Boundary.                                    |
|                                                                              |
| "Corrective Action(s):  Additional inspections will be performed to          |
| determine the cause of identified boron accumulation."                       |
|                                                                              |
| Unit 3 is currently in mode 5 (Cold Shutdown) depressurized to atmosphere    |
| with RCS temperature at 120 degrees F.  The licensee is making preparations  |
| to enter mode 6 (Refueling) in order to lift the RV Head.  The licensee      |
| informed the NRC resident inspector.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37761       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 02/19/2001|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 03:00[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        02/18/2001|
+------------------------------------------------+EVENT TIME:        22:45[EST]|
| NRC NOTIFIED BY:  VICTOR WALZ                  |LAST UPDATE DATE:  02/19/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLIFFORD ANDERSON    R1      |
|10 CFR SECTION:                                 |JOHN ZWOLINSKI       NRR     |
|*IND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION SYSTEM (HPCI) DECLARED INOPERABLE            |
|                                                                              |
| "During normal monitoring of the standby lineup of the High Pressure Coolant |
| Injection System (HPCI), the building rounds operator noticed that the HPCI  |
| discharge flow switch (23FS-78) was indicating 140 gpm with zero actual      |
| flow.  This flow switch controls the operation of the HPCI pump minimum flow |
| valve during HPCI operations.  Upon further investigation by the operating   |
| crew, it was also determined that the HPCI pump discharge flow transmitter   |
| was exhibiting sporadic flow spikes of 50 to 100 gpm with zero system flow.  |
| This flow signal is used to control HPCI turbine speed and flowrate.  Based  |
| on these findings, the HPCI system was declared inoperable per Technical     |
| Specification 3.5.c and a 7 day Limiting Condition for Operation was         |
| entered."                                                                    |
|                                                                              |
| The licensee called in an engineering team to address this problem.  The     |
| licensee will inform the NRC resident inspector.                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37762       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FARLEY                   REGION:  2  |NOTIFICATION DATE: 02/19/2001|
|    UNIT:  [1] [2] []                STATE:  AL |NOTIFICATION TIME: 13:04[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        02/19/2001|
+------------------------------------------------+EVENT TIME:        06:12[CST]|
| NRC NOTIFIED BY:  BRAD MOORE                   |LAST UPDATE DATE:  02/19/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANNE BOLAND          R2      |
|10 CFR SECTION:                                 |                             |
|*COM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| LOSS OF EMERGENCY COMMUNICATIONS TO THE STATE                                |
|                                                                              |
| The licensee lost the emergency communications line to the states of Alabama |
| and Georgia at 0512 CST on 2/19/01 due to the failure of a communications    |
| power inverter located offsite in Dothan, Alabama.  The inverter was         |
| restored at 0758 CST, restoring the emergency communications line.  All      |
| other communications were available during this time.                        |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37763       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FLORIDA BUREAU OF RADIATION CONTROL  |NOTIFICATION DATE: 02/19/2001|
|LICENSEE:  QUALITY INSPECTION SERVICES, INC.    |NOTIFICATION TIME: 13:47[EST]|
|    CITY:  JACKSONVILLE             REGION:  2  |EVENT DATE:        02/16/2001|
|  COUNTY:                            STATE:  FL |EVENT TIME:        12:30[EST]|
|LICENSE#:  3043-1                AGREEMENT:  Y  |LAST UPDATE DATE:  02/19/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ANNE BOLAND          R2      |
|                                                |E. WILLIAM BRACH     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHARLES ADAMS                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT OF PERSONNEL OVEREXPOSURE                             |
|                                                                              |
| The following is a portion of the information provided:                      |
|                                                                              |
| "Approximately 12:30 am February 16 following a shoot, the source was reeled |
| into what was thought to be a locked position. A complete survey was not     |
| done to confirm position of the source. The two individuals involved         |
| proceeded in front of the camera to set up the next shot, taking less than 5 |
| minutes. When they went to unlock the source they realized that it was not   |
| locked and noticed the survey meter was off scale. They exited the area and  |
| fully retracted the source. Both pocket dosimeters were off scale. One rate  |
| alarm meter was turned off and the other had a low battery and did not give  |
| a audio alarm. Film badges showed 2.9 and 39.2 R exposure. The individual    |
| with the high exposure has had blood drawn for analysis but no results are   |
| available yet. Landauer has been asked recheck the film badge readings. The  |
| wrong state office was notified 16 February. This office was notified 19     |
| February."                                                                   |
|                                                                              |
| The camera contains a 58 Ci source of Ir-192.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37764       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 02/19/2001|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 15:24[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        02/19/2001|
+------------------------------------------------+EVENT TIME:        12:00[EST]|
| NRC NOTIFIED BY:  KENNETH RUSSELL              |LAST UPDATE DATE:  02/19/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PATRICK HILAND       R3      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| THE OHIO EPA NOTIFIED OF AN UNINTENTIONAL DISCHARGE OF CONDENSER COOLING     |
| WATER                                                                        |
|                                                                              |
| The Ohio EPA was notified of an unintentional bypass of the wastewater       |
| treatment system as required by the NPDES Permit.  No reportable quantities  |
| were discharged.  This was a non-radioactive effluent, main condenser        |
| cooling water.                                                               |
|                                                                              |
| The license intends to notify the NRC Resident Inspector.                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37765       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 02/19/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 23:38[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        02/19/2001|
+------------------------------------------------+EVENT TIME:        20:30[CST]|
| NRC NOTIFIED BY:  DUANE SCHMIDT                |LAST UPDATE DATE:  02/19/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PATRICK HILAND       R3      |
|10 CFR SECTION:                                 |                             |
|*UNA 50.72(b)(3)(ii)(B)  UNANALYZED COND OP     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION FOR RESIDUAL HEAT REMOVAL CAPABILITY                    |
|                                                                              |
| The licensee has determined that torus cooling initiation has not been       |
| validated as part of operator actions to be initiated within 10 minutes of a |
| design basis accident in the containment.   The licensee, as an interim      |
| action, has added an extra licensed operator whose only responsibility is    |
| the initiation of torus cooling at the direction of the emergency operating  |
| procedures.  Further analysis is being carried out for a final resolution.   |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37766       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 02/20/2001|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 01:56[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        02/19/2001|
+------------------------------------------------+EVENT TIME:        21:08[CST]|
| NRC NOTIFIED BY:  JOHN MYERS                   |LAST UPDATE DATE:  02/20/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GREG PICK            R4      |
|10 CFR SECTION:                                 |                             |
|*SHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |54       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECH SPEC REQUIRED SHUTDOWN COMMENCED AFTER DECLARING BOTH STANDBY GAS       |
| TREATMENT (SGT) TRAINS INOPERABLE                                            |
|                                                                              |
| "While performing Surveillance 6.SUMP.101, Z SUMP AND AIR EJECTOR HOLDUP     |
| LINE DRAIN OPERABILITY TEST (IST), Z-1 sump pump exceeded its operability    |
| time limit of 151 seconds by 3 seconds. When Z-2 sump pump was subsequently  |
| tested, the pump failed to start on the essential HI-HI level switch.  Both  |
| sump pumps were declared INOPERABLE. These pumps support Standby Gas         |
| Treatment OPERABILITY. The SGT line from the plant runs underground to the   |
| Elevated Release Point tower, and the offgas line and SGT both enter this    |
| sump. The pumps remove condensation from both the offgas lines and SGT, and  |
| must be available post-accident to prevent flooding of the SGT lines.        |
|                                                                              |
| "Per administrative direction in the Surveillance procedure, both trains of  |
| SGT were declared INOPERABLE at 2108.  Per Technical Specification 3.6.4.3,  |
| Condition D, with two SGT subsystems INOPERABLE in Mode 1, the Required      |
| Action is to enter LCO 3.0.3 immediately.  LCO 3.0.3 requires the plant to   |
| be in Mode 2 within 7 hours, Mode 3 within 13 hours, and Mode 4 within 37    |
| hours.  A power reduction was commenced at 2250. Present power level is      |
| 54%.                                                                         |
|                                                                              |
| "Engineering personnel have responded to the plant and are evaluating the    |
| two conditions."                                                             |
|                                                                              |
| The above surveillance is performed quarterly.  The licensee noted a past    |
| history of problems with the system's level switches.  The current rate of   |
| power reduction is approximately 100 MW/hr or 12-15% reactor power. The      |
| licensee informed the NRC resident inspector.                                |
|                                                                              |
| * * * UPDATE 0441 2/20/01 FROM TERRY BORGAN TO S. SANDIN * * *               |
|                                                                              |
| Tech Spec required shutdown exited at 0334CST after engineering determined   |
| that one train of SGT was OPERABLE.  The Unit remains in a 7-day LCO for the |
| other INOPERABLE train.  Notified R4DO(Pick).                                |
+------------------------------------------------------------------------------+