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Event Notification Report for April 24, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           04/23/2003 - 04/24/2003



                              ** EVENT NUMBERS **



39769  39784  39785  39786  39787  39788  39789  39790  39791  



+------------------------------------------------------------------------------+

|General Information or Other                     |Event Number:   39769       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| REP ORG:  OHIO BUREAU OF RADIATION PROTECTION  |NOTIFICATION DATE: 04/18/2003|

|LICENSEE:  SOLAR TESTING LABORATORIES           |NOTIFICATION TIME: 09:31[EDT]|

|    CITY:  BROOKLYN HEIGHTS         REGION:  3  |EVENT DATE:        04/18/2003|

|  COUNTY:                            STATE:  OH |EVENT TIME:             [EDT]|

|LICENSE#:  OH31210180065         AGREEMENT:  Y  |LAST UPDATE DATE:  04/18/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |THOMAS KOZAK         R3      |

|                                                |MATT KORMANN         TAT     |

+------------------------------------------------+FRED BROWN           NMSS    |

| NRC NOTIFIED BY:  MIKE SNEE                    |                             |

|  HQ OPS OFFICER:  MIKE RIPLEY                  |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+------------------------------------------------------------------------------+



                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| THEFT AND RECOVERY OF MOISTURE DENSITY GAUGE                                 |

|                                                                              |

| The following information was received via facsimile from the Ohio           |

| Department of Health:                                                        |

|                                                                              |

| The licensee reported the theft and recovery of a Humboldt Scientific        |

| moisture/density gauge (model 5001, serial #750) containing a 44 millicurie  |

| Am-Be source and a 11 millicurie Cs-137 source.  The gauge was stolen during |

| the early hours of April 18, 2003 from the back of a truck parked at an      |

| employee's residence in Brooklyn Heights, Ohio. The truck and gauge case was |

| broken into.  The licensee notified police and the Ohio Department of        |

| Health.   At 8:45 AM on April 18, the employee discovered the gauge on the   |

| side of the road a short distance from his residence where the theft         |

| occurred.  The gauge did not appear to be damaged.                           |

|                                                                              |

| Notified R3DO (T. Kozak), NMSS (F. Brown), NSIR IAT (M. Kormann)             |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39784       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 04/23/2003|

|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 05:29[EDT]|

|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        04/23/2003|

+------------------------------------------------+EVENT TIME:        02:07[EDT]|

| NRC NOTIFIED BY:  TOM DOUGHERTY                |LAST UPDATE DATE:  04/23/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |HAROLD GRAY          R1      |

|10 CFR SECTION:                                 |                             |

|ACCS 50.72(b)(2)(iv)(A)  ECCS INJECTION         |                             |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |

|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     M/R        Y       100      Power Operation  |0        Hot Shutdown     |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| RPS ACTUATION WHILE CRITICAL                                                 |

|                                                                              |

| "At 0207 EDT on April 23, 2003, a loss of feedwater occurred on Unit 1.      |

| Operators initiated a manual reactor scram at 15 [inches] RPV level (auto    |

| scram signal = 12.5 [inches]). The high pressure coolant injection (HPCI)    |

| and reactor core isolation coolant (RCIC) systems initiated as designed at   |

| -38 [inches], and injected into the RPV.  RPV level was restored to the      |

| normal band, HPCI and RCIC secured, and a reactor feed pump was returned to  |

| service.  The following isolation signals were received;  Groups IB, IIA,    |

| IIC, III, VIB, VIC, VIIB, VIIIB, and HVAC.  RPV and containment parameters   |

| are normal with an RPV cooldown in progress.                                 |

|                                                                              |

| "The loss of feed resulted from sequential trips of all 3 reactor feed pumps |

| on low suction pressure due to an apparent isolation of the condensate deep  |

| bed demineralizers.  The cause is under investigation."                      |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39785       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 04/23/2003|

|    UNIT:  [2] [3] []                STATE:  PA |NOTIFICATION TIME: 10:23[EDT]|

|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        03/21/2003|

+------------------------------------------------+EVENT TIME:        12:19[EDT]|

| NRC NOTIFIED BY:  DAVID J. FOSS                |LAST UPDATE DATE:  04/23/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |HAROLD GRAY          R1      |

|10 CFR SECTION:                                 |                             |

|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|2     N          Y       100      Power Operation  |100      Power Operation  |

|3     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| INVALID SPECIFIED SYSTEM ACTUATION                                           |

|                                                                              |

| "This 60-day optional report, as allowed by 10 CFR 50.73(a)(1), is being     |

| made under the reporting requirement in 10 CFR 50.73(a)(iv)(A) to describe   |

| an unplanned, invalid actuation of a specified system, specifically the E-2  |

| Emergency Diesel Generator (EDG).                                            |

|                                                                              |

| "On March 21, 2003, a momentary short was created during the installation of |

| test jacks, which resulted in an invalid start signal to the E-2 EDG.  The   |

| E-2 EDG started, however, the associated emergency buses remained energized  |

| from their normal power supplies.                                            |

|                                                                              |

| "The affected emergency diesel generator responded as expected for the given |

| conditions and was subsequently returned to a normal configuration per plant |

| procedures.  No deficiencies or abnormalities were noted during the event.   |

|                                                                              |

| "This event has been entered into the site-specific corrective action        |

| program for resolution.                                                      |

|                                                                              |

| "The NRC resident has been informed."                                        |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39786       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 04/23/2003|

|    UNIT:  [] [2] []                 STATE:  TN |NOTIFICATION TIME: 12:43[EDT]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/08/2003|

+------------------------------------------------+EVENT TIME:        12:11[EDT]|

| NRC NOTIFIED BY:  M. HOWARD                    |LAST UPDATE DATE:  04/23/2003|

|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MIKE ERNSTES         R2      |

|10 CFR SECTION:                                 |                             |

|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|2     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| INVALID UNIT 2 TRAIN "B" CONTAINMENT VENT ISOLATION (CVI) .                  |

|                                                                              |

| On 04/08/03 at 1211 an invalid Unit 2, Train "B", Containment Vent Isolation |

| (CVI) occurred.  The actuation was caused by increased sensitivity of        |

| radiation monitor 2-RM-90-131 as a result of small perforations in the       |

| aluminum foil cover of the detector.                                         |

|                                                                              |

| The specific train actuated was Train "B", and the system which received the |

| isolation signal were Containment Ventilation Purge and EXHAUST (already     |

| closed) and Radiation Monitoring isolation valves (went closed).             |

|                                                                              |

| Complete train actuation occurred.                                           |

|                                                                              |

| The Containment Ventilation Isolation function was successful.               |

|                                                                              |

| The NRC Resident  Inspector was notified of this event by the licensee.      |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39787       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 04/23/2003|

|    UNIT:  [1] [2] []                STATE:  TN |NOTIFICATION TIME: 12:46[EDT]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/12/2003|

+------------------------------------------------+EVENT TIME:        12:54[EDT]|

| NRC NOTIFIED BY:  M. HOWARD                    |LAST UPDATE DATE:  04/23/2003|

|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MIKE ERNSTES         R2      |

|10 CFR SECTION:                                 |                             |

|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          N       0        Refueling        |0        Refueling        |

|2     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| INVALID START OF  THE FOUR  EMERGENCY DIESEL GENERATORS.                     |

|                                                                              |

| On 04/12/03 at 1254 an invalid start of the four emergency diesel generators |

| occurred.  The actuation was caused by a loss of DC power to the 1BB         |

| emergency diesel start circuit and a auto start signal to the  remaining 3   |

| emergency diesel generators.  Power loss was caused by poor terminal lug     |

| contact on a space breaker during testing of a Vital Battery breaker.        |

|                                                                              |

| The specific train actuated were both Train "A" and "B" for both Units 1 and |

| 2.  The system actuated was emergency AC electrical power (emergency diesel  |

| generators).                                                                 |

|                                                                              |

| Complete train actuation occurred.                                           |

|                                                                              |

| The Emergency Diesel Generator start was successful.                         |

|                                                                              |

| The NRC Resident Inspector was notified of this event by the licensee.       |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39788       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 04/23/2003|

|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 23:44[EDT]|

|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        04/23/2003|

+------------------------------------------------+EVENT TIME:        19:55[CDT]|

| NRC NOTIFIED BY:  MARK OKOPNY                  |LAST UPDATE DATE:  04/23/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MONTE PHILLIPS       R3      |

|10 CFR SECTION:                                 |                             |

|ACOM 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       67       Power Operation  |67       Power Operation  |

|2     N          Y       10       Power Operation  |100      Power Operation  |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| LOST OF EMERGENCY ASSESSMENT CAPABILITY                                      |

|                                                                              |

| "This report is being made pursuant to 10CFR50.72(b)(3)(xiii) Major loss of  |

| emergency assessment capability. During the performance of routine           |

| surveillance LOS-VG-M1 Standby Gas Treatment System Operability Test and     |

| Inservice Test of 1VG001 and 1VG003, it was reported that the installed      |

| preplanned monitoring system sample pump tripped. At 19:55 CDST on April     |

| 23rd it was confirmed that the sample pump had tripped for the Preplanned    |

| Alternate sampling system. This Preplanned Alternate sampling system had     |

| been connected to comply with the Technical Requirements Manual (TRM) from   |

| the inoperability of the installed Standby Gas Treatment Stack monitoring    |

| system (Standby Gas Treatment system Wide Range Gas Monitoring system -SBGT  |

| WRGM). Troubleshooting is in progress to restore the Preplanned Alternate    |

| sample pump. The Standby Gas Treatment Train has been secured and placed in  |

| standby configuration. The plant is stable and no abnormal or elevated       |

| release occurred during this event."                                         |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39789       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 04/24/2003|

|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 01:25[EDT]|

|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        04/23/2003|

+------------------------------------------------+EVENT TIME:        19:23[CDT]|

| NRC NOTIFIED BY:  MARK OKOPNY                  |LAST UPDATE DATE:  04/24/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MONTE PHILLIPS       R3      |

|10 CFR SECTION:                                 |                             |

|AIND 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       67       Power Operation  |67       Power Operation  |

|                                                   |                          |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| ACCIDENT MITIGATION                                                          |

|                                                                              |

| "This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or      |

| Condition that could have prevented fulfillment of a Safety Function needed  |

| to Mitigate the Consequences of an Accident. On 04/23/03, at 18:15 CDST, the |

| 1A Diesel Generator was made inoperable for a scheduled surveillance.        |

| Concurrent with this inoperability, the 0 Diesel Generator received a        |

| spurious CO2 actuation signal. This spurious CO2 partial logic actuation did |

| not result in an actual CO2 injection into the 0 Diesel Generator Room. The  |

| CO2 system partial actuation however resulted in several ventilation dampers |

| failing closed as designed. With these dampers closed, the ventilation       |

| support system for the 0 Diesel Generator became inoperable, the 0 Diesel    |

| Generator was declared inoperable at 1923 hours 04/23/03. This condition     |

| resulted in both the 1A and 0 Diesel Generators concurrently being           |

| inoperable. Actions were taken to terminate the 1A Diesel surveillance and   |

| restore the 1A Diesel Generator to an operable status. This was accomplished |

| at 1952 hours 04/23/03. The 1A and 0 Diesel Generators were simultaneously   |

| inoperable for 29 minutes. Due to the concurrent Diesel Generator            |

| inoperabilities which affect redundant trains required to mitigate the       |

| consequences of an accident, it has been determined that this event is       |

| reportable as an 8 hour ENS notification.                                    |

|                                                                              |

| "Corrective actions have been initiated to address the 0 Diesel Generator    |

| CO2 system and restore the ventilation dampers to an operable status. The    |

| spurious actuation of the 0 Diesel Generator CO2 system was determined to be |

| due to a Non-Licensed Operator opening the fire detection panel for          |

| inspection."                                                                 |

|                                                                              |

| The licensee notified the NRC Resident Inspector.                            |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39790       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 04/24/2003|

|    UNIT:  [1] [2] []                STATE:  MI |NOTIFICATION TIME: 04:40[EDT]|

|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/24/2003|

+------------------------------------------------+EVENT TIME:        03:48[EDT]|

| NRC NOTIFIED BY:  STUART SCHUETTPELZ           |LAST UPDATE DATE:  04/24/2003|

|  HQ OPS OFFICER:  ERIC THOMAS                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          ALERT                 |MONTE PHILLIPS       R3      |

|10 CFR SECTION:                                 |JAMES LYONS          NRR     |

|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |MICHELE EVANS        IRO     |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|CHUCK CAIN           R4      |

|                                                |CHARLIE BAGWELL      FEMA    |

|                                                |JOHN FLACH           NRC     |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     M/R        Y       100      Power Operation  |0        Hot Standby      |

|2     M/R        Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| ALERT DECLARED                                                               |

|                                                                              |

| At 0348 EDT on 4/24/03, the plant experienced an influx of fish on the       |

| intake screens for the circwater and emergency service water (ESW) systems.  |

| This resulted in a loss of vacuum to Units 1 and 2 main turbines, which led  |

| operators to manually trip both reactors.  Following the trip, operators     |

| noted that ESW flow to all 4 emergency diesel generators (EDGs) was severely |

| degraded.  This resulted in the licensee declaring all 4 EDG's inoperable.   |

| An alert was declared at 0348 EDT, and the NRC entered Monitoring Mode at    |

| 0506 EDT.                                                                    |

|                                                                              |

| * * * UPDATE AT 0600 FROM LICENSEE TO H. CROUCH * * *                        |

|                                                                              |

| All EDG's have adequate flow to be used in an emergency, but remain          |

| inoperable.                                                                  |

|                                                                              |

| The licensee is assessing damage to intake screens and strainers in the ESW  |

| system, and manually backwashing ESW screens.                                |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Fuel Cycle Facility                              |Event Number:   39791       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 04/24/2003|

|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 05:42[EDT]|

| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        04/24/2003|

|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:             [CDT]|

|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  04/24/2003|

|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+

|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |

|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MONTE PHILLIPS       R3      |

|  DOCKET:  0707001                              |DANIEL GILLEN        NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  TOM WHITE                    |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NBNL                     RESPONSE-BULLETIN      |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+------------------------------------------------------------------------------+



                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| CRITICALITY CONTROL 24-HOUR REPORT (RESPONSE BULLETIN 91-01)                 |

|                                                                              |

| The following information was obtained from the regulatee via facsimile:     |

|                                                                              |

| "At 1320 [CDT] on 4/23/03, the Plant Shift Superintendent (PSS) was notified |

| that the trap media replacement activities for C-337 #4 Seal Exhaust (SX)    |

| trap were performed on 4/6/03 through 4/8/03 and the trap media and the      |

| bottom screen were replaced.  Contrary to the requirements of NCSA CAS-007,  |

| 'independent verification of no trap media below the bottom screen' was not  |

| performed prior to the bottom flange being removed.  This requirement        |

| ensures that an unanalyzed volume of media does not spill from the trap.     |

|                                                                              |

| "The NRC Resident Inspector has been notified of the event.                  |

|                                                                              |

| "PDGP Assessment and Tracking Report No. ATR 03-1199 PGDP Event Report No.   |

| PAD-2003-008 NRC Event Worksheet [39791].                                    |

|                                                                              |

| "Responsible Division: Maintenance                                           |

|                                                                              |

| "SAFETY SIGNIFICANCE OF EVENTS:                                              |

|                                                                              |

| "Although the trap was not independently verified to be essentially empty of |

| accumulated trap mix, prior to in-place maintenance, no media was found when |

| the bottom flange was removed.                                               |

|                                                                              |

| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(s) OF HOW C         |

| RITICALITY COULD OCCUR):                                                     |

|                                                                              |

| "In order for a criticality to be possible, a critical volume of trap mix    |

| would have to be accumulated in an unsafe geometry.                          |

|                                                                              |

| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION. ETC:      |

|                                                                              |

| "Double contingency is maintained by implementing two controls on volume.    |

|                                                                              |

| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS    |

| LIMIT AND % WORST CASE CRITICAL MASS):                                       |

|                                                                              |

| "There was no media found when the bottom flange was removed.                |

|                                                                              |

| "NUCLEAR CRITICALITY SAFETY CONTROL (S) OR CONTROL SYSTEM(S) AND DESCRIPTION |

| OF THE FAILURES OR DEFICIENCES:                                              |

|                                                                              |

| "The first leg of double contingency relies on controlling the volume of     |

| trap mix available to be spilled from the, trap after removal of media above |

| the bottom screen. NCSA CAS-007 requires the trap to be verified emptied of  |

| trap media prior to in-place maintenance, thus ensuring that the trap does   |

| not contain any accumulated trap mix in excess of a 5.5-gal drum.            |

| Verification of the trap mix accumulated in the trap was not done, thus,     |

| this control was violated.                                                   |

|                                                                              |

| "The second leg of double contingency relies on controlling the volume of    |

| trap mix available to be spilled from the trap after removal of media above  |

| the bottom screen. NCSA CAS-007 requires the trap to be independently        |

| verified emptied of trap media prior to in-place maintenance. Independent    |

| verification of the trap mix accumulated in the trap was not performed.      |

| therefore. this control was violated. Neither of the controls (verification  |

| and independent verification) of the single parameter (volume) were          |

| performed and double contingency was not maintained.                         |

|                                                                              |

| "No trap media was spilled from the trap, thus maintaining the volume        |

| parameter.                                                                   |

|                                                                              |

| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: |

|                                                                              |

|                                                                              |

| "None."                                                                      |

|                                                                              |

| Operations notified the NRC resident inspector.                              |

+------------------------------------------------------------------------------+