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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Event Notification Report for 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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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).                                |
+------------------------------------------------------------------------------+


Page Last Reviewed/Updated Wednesday, March 24, 2021