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Event Notification Report for May 21, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           05/20/2003 - 05/21/2003



                              ** EVENT NUMBERS **



39850  39853  39862  39863  39864  39865  39866  39867  39869  39870  



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

|General Information or Other                     |Event Number:   39850       |

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

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

| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 05/15/2003|

|LICENSEE:  BLAZER INDUSTRIAL RADIOGRAPHY        |NOTIFICATION TIME: 12:18[EDT]|

|    CITY:  PASADENA                 REGION:  4  |EVENT DATE:        05/14/2003|

|  COUNTY:                            STATE:  TX |EVENT TIME:        18:48[CDT]|

|LICENSE#:  LO4619                AGREEMENT:  Y  |LAST UPDATE DATE:  05/16/2003|

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

|                                                |PERSON          ORGANIZATION |

|                                                |WILLIAM JOHNSON      R4      |

|                                                |TOM ESSIG            NMSS    |

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

| NRC NOTIFIED BY:  HELEN WATKINS                |                             |

|  HQ OPS OFFICER:  ERIC THOMAS                  |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| AGREEMENT STATE REPORT                                                       |

|                                                                              |

| The licensee reported a potential overexposure to a radiographer who was     |

| x-raying some pipes at a worksite.  After completing a section of piping,    |

| the radiographer should have cranked his source back in, but was interrupted |

| by another technician and left his work area.  When he returned, the         |

| radiographer changed out his film, and moved the guide tube to another       |

| section of piping to begin more x-rays.  At this point, he realized that his |

| survey meter had pegged high, and remembered that he had not cranked the     |

| source back in prior to moving it.  He proceeded to immediately crank the    |

| source back to its fully shielded position.  The exact time and distance     |

| from the source for the radiographer's exposure is unknown, and the licensee |

| is attempting to re-create the scenario.                                     |

|                                                                              |

| The source was 26 Curies of Iridium 192, model number INC-32.  The serial    |

| number is unknown at this time.  A preliminary investigation by the licensee |

| estimates the radiographer's exposure to 800-900 millirem whole body.  There |

| is currently no exposure estimate for his hands/extremities.                 |

|                                                                              |

| The radiographer's badge was sent off for processing.  Results will be       |

| reported on 5/16/03 to the NRC.  The Texas Department of Health is sending   |

| an additional inspector to the site to investigate.                          |

|                                                                              |

|                                                                              |

| * * * UPDATE ON 5/16/03  @ 1120 BY  WATKINS TO GOULD * * *                   |

|                                                                              |

| Blazer Industrial Radiography brought in a consultant to perform preliminary |

| dose calculations for the whole body and the right hand of the radiographer. |

| The results were 1.3R for the whole body and 37.1R for the right hand,       |

| neither of which exceeds the annual regulatory limit.                        |

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



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

|Fuel Cycle Facility                              |Event Number:   39853       |

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

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

| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 05/16/2003|

|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 10:04[EDT]|

| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/15/2003|

|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        14:00[EDT]|

|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/21/2003|

|    CITY:  PIKETON                  REGION:  3  +-----------------------------+

|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |

|LICENSE#:  GDP-2                 AGREEMENT:  N  |SONIA BURGESS        R3      |

|  DOCKET:  0707002                              |TOM ESSIG            NMSS    |

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

| NRC NOTIFIED BY:  MCCLEERY                     |                             |

|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|QSAF 72.75(c)(2)         SAFETY EQUIP DISABLED/F|                             |

|NONR                     OTHER UNSPEC REQMNT    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| SAFETY SYSTEM ACTUATION                                                      |

|                                                                              |

| On 5/15/03 @1400 during pigtail disconnect, a small amount of particulate    |

| fell from the pigtail. This particulate began to smoke resulting in a see    |

| and flee.  During the see and flee the gas release alarm was activated.  The |

| alarm resulted in the actuation of a "Q" Safety system while in applicable   |

| mode (mode III).  The PSS Responded to the see and flee.  The affected       |

| cylinder was made inoperable.  No spread of contamination outside already    |

| posted area.   Air sampling results are less than MDA.                       |

|                                                                              |

| The NRC Resident Inspector was notified.                                     |

|                                                                              |

| * * * UPDATE AT 23:46 EDT ON 5/20/03 FROM McCLEERY TO CROUCH * * *           |

|                                                                              |

| The following update was received from the regulatee via facsimile:          |

|                                                                              |

| "5/20/05: As requested, this is additional information to clarify some       |

| questions in the initial report of PTS-2003-011.  Mode III (Cylinder/Pigtail |

| Operations) includes but is not limited to pigtail                           |

| connection/disconnections, roll/tilt and valve clarity checks; steam valves  |

| closed, cylinder valve or safety valve may or may not be closed.  MDA is     |

| minimum detectable activity.  The initial report should have been marked as  |

| Other Non-CFR Requirements in place of (c)(2) safety equipment failure.      |

|                                                                              |

| Additionally, during the investigation of the event it was determined the    |

| cylinder safety valve air supply was removed prior to the see and flee.      |

| This condition is reportable under 76.120 (c)(2)(ii) [and] 76.120 (d)(2).    |

| The equipment is required by Technical Safety Requirements (TSR) to be       |

| available and operable to perform the required safety function, while the    |

| autoclave is operating in mode III (cylinder/ pigtail operations).           |

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



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

|Power Reactor                                    |Event Number:   39862       |

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

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

| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 05/20/2003|

|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 02:47[EDT]|

|   RXTYPE: [1] GE-2                             |EVENT DATE:        05/20/2003|

+------------------------------------------------+EVENT TIME:        00:30[EDT]|

| NRC NOTIFIED BY:  JEFF DOSTAL                  |LAST UPDATE DATE:  05/20/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |ANTHONY DIMITRIADIS  R1      |

|10 CFR SECTION:                                 |MICHAEL CASE         NRR     |

|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |RICHARD WESSMAN      IRO     |

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

|                                                |JIM WIGGINS          R1      |

|                                                |NEAL PERRY           R1      |

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

|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                                   

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

| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS                          |

|                                                                              |

| The plant experienced a trip of the "C" 4160 V electrical bus.  This         |

| condition required entry into multiple technical specifications the most     |

| limiting being 3.3.D.5.B due to the loss of the capability to determine the  |

| rate of identified containment leakage.  This required the reactor to be     |

| placed in a shutdown condition within the next 12 hours.                     |

|                                                                              |

| The licensee believes that the cause of the "C" bus trip is a fault on the   |

| bus that is indicated as a lockout, however, the specific fault is unknown   |

| at this time and is under investigation.  Due to the faulted bus, the        |

| station's emergency diesel generator did not start and will not be able to   |

| power any equipment on the "C" bus until the fault is repaired.  Significant |

| safety equipment lost due to loss of the bus is as follows:                  |

|                                                                              |

| Emergency Service Water pump and Containment spray system #1                 |

| Service Water pump #1                                                        |

| Reactor Building Closed Cooling pump #1                                      |

| Standby Gas Treatment system #1                                              |

| Core spray and Core spray booster pumps "A" & "D" (4 pumps total)            |

| Standby Liquid Control pump #1                                               |

| Control Rod Drive pump #1                                                    |

|                                                                              |

| The plant is commencing the required shutdown and expect to be at 60%        |

| reactor power by 0430 EDT.                                                   |

|                                                                              |

| The licensee will be notifying the NRC Resident Inspector.                   |

|                                                                              |

| * * * UPDATE AT 1040 EDT ON 5/20/03 FROM PEZZELLA TO CROUCH * * *            |

|                                                                              |

| As a result of the loss of 4160 VAC,  the safeguards system became degraded. |

| Immediate compensatory measures were taken upon discovery.  Contact the      |

| Headquarters Operations Officer for details.                                 |

|                                                                              |

| * * * UPDATE AT 1245 EDT ON 5/20/03 FROM PIETRUSKI TO THOMAS * * *           |

|                                                                              |

| The plant initiated an unplanned reactor manual scram from 60 percent power  |

| at 0945 ET.  This event was reported per 10 CFR 50.72(b)(2)(iv)(B): 'Any     |

| event or condition that results in actuation of the reactor protection       |

| system (RPS) when the reactor is critical except when the actuation results  |

| from and is part of a pre-planned sequence during testing or reactor         |

| operation.                                                                   |

|                                                                              |

| The licensee had planned to scram the plant from 30 percent power, but       |

| because of the loss of "C" 4160V electrical bus, they were unable to remove  |

| the second stage reheaters and feedwater heaters from service, and were thus |

| limited by procedure from lowering power to the desired level prior to       |

| inserting a scram.                                                           |

|                                                                              |

| The licensee notified the NRC Resident Inspector.  Notified NRR EO (T. Reis, |

| R. Dennig), DIRO (M. Evans), R1DO (A. Dimitriadis)                           |

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



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

|Power Reactor                                    |Event Number:   39863       |

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

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

| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 05/20/2003|

|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 07:30[EDT]|

|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        05/20/2003|

+------------------------------------------------+EVENT TIME:        03:25[CDT]|

| NRC NOTIFIED BY:  DARYL CLARK                  |LAST UPDATE DATE:  05/20/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |ANNE MARIE STONE     R3      |

|10 CFR SECTION:                                 |CYNTHIA CARPENTER    NRR     |

|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |TERRY REIS           NRR     |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|1     N          N       0        Startup          |0        Startup          |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS DUE TO REACTOR COOLANT   |

| BOUNDARY LEAKAGE                                                             |

|                                                                              |

| The following information was received from the licensee via facsimile:      |

|                                                                              |

| "At 0325 hours CDT on 5/20/2003, the Unit One Reactor Coolant System was     |

| determined to have Pressure Boundary Leakage. The Unit was in the process of |

| shutting down for a maintenance outage, and subcritical at the time. The     |

| leakage was found during a Drywell inspection as part of the shutdown. The   |

| leak was located upstream of the isolation valves on the reactor head vent   |

| line. The Technical Specification Required Action for this Condition         |

| (Technical Specification 3.4.4, Condition C) is for the Unit to be in Mode 3 |

| in 12 hours and be in Mode 4 in 36 hours.                                    |

|                                                                              |

| "This notification is being made in accordance with 10 CFR 50.72(b)(2)(i)."  |

|                                                                              |

| The licensee is unable to quantify the leak at this time and is unable to    |

| determine if the this was a long-term leak.  Unit 1 entered Mode 3 (Hot      |

| Shutdown) at 0607 CDT.                                                       |

|                                                                              |

| The NRC Resident Inspector was notified by the licensee.                     |

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



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

|Power Reactor                                    |Event Number:   39864       |

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

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

| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 05/20/2003|

|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 08:27[EDT]|

|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        05/20/2003|

+------------------------------------------------+EVENT TIME:        04:53[EDT]|

| NRC NOTIFIED BY:  JOHN YADUSKY                 |LAST UPDATE DATE:  05/20/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |ROBERT HAAG          R2      |

|10 CFR SECTION:                                 |                             |

|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       20       Power Operation  |0        Hot Standby      |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| MANUAL REACTOR TRIP DUE TO LOSS OF OPERATING MAIN FEED PUMP                  |

|                                                                              |

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

|                                                                              |

| "At 0453 on 05/20/03 with the reactor at approximately 20 percent power in   |

| MODE 1, the reactor was manually tripped in response to an automatic trip of |

| the operating Main Feed Pump (MFP).  Both motor-driven Auxiliary Feedwater   |

| (AFW) pumps started due to the trip of the MFP.  Safety systems functioned   |

| as required.  The operations crew responded to the event in accordance with  |

| applicable plant procedures.  The plant was stabilized at normal operating   |

| no-load Reactor Coolant System temperature and pressure following the        |

| reactor trip.  The cause of the MFP trip is still under investigation.       |

| This condition is being reported as actuations of the reactor protection     |

| system and AFW in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR       |

| 50.72(b)(3)(iv)(A)."                                                         |

|                                                                              |

| According to the licensee, the MFP tripped after loss of the "A" condensate  |

| booster pump.                                                                |

|                                                                              |

| After the manual trip, all control rods inserted into the core.  There were  |

| no primary relief valves actuated during the resulting transient.  Main      |

| Steam Isolation Valves were closed during the trip therefore decay heat is   |

| being removed via AFW and the steam generator power operated relief valves.  |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

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



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

|Power Reactor                                    |Event Number:   39865       |

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

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

| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 05/20/2003|

|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 08:51[EDT]|

|   RXTYPE: [1] GE-2                             |EVENT DATE:        05/20/2003|

+------------------------------------------------+EVENT TIME:        06:50[EDT]|

| NRC NOTIFIED BY:  JEFF DOSTAL                  |LAST UPDATE DATE:  05/20/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |ANTHONY DIMITRIADIS  R1      |

|10 CFR SECTION:                                 |                             |

|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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

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

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

|1     N          Y       60       Power Operation  |60       Power Operation  |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| OFFSITE NOTIFICATION TO NEW JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION    |

|                                                                              |

| At 0650 EDT on 5/20/03,  the licensee notified the State of New Jersey       |

| Department of Environmental Protection due to an impending planned scram.    |

| Additionally, they notified the same agency that Oyster Creek will have a    |

| potential non-compliance based on the plant canal temperature recorder       |

| losing power (see event #39862).  This is a potential violation of the       |

| plant's New Jersey Pollution Discharge Elimination System permit.            |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

|                                                                              |

| * * * UPDATE AT 1100 EDT ON 5/20/03 FROM DOSTAL TO CROUCH * * *              |

|                                                                              |

| The licensee will be issuing a press release based on loss of 4160 VAC bus   |

| and resulting plant shutdown.                                                |

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



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

|Power Reactor                                    |Event Number:   39866       |

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

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

| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 05/20/2003|

|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 11:39[EDT]|

|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        05/20/2003|

+------------------------------------------------+EVENT TIME:        09:16[EDT]|

| NRC NOTIFIED BY:  JEFF GRANT                   |LAST UPDATE DATE:  05/20/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |ROBERT HAAG          R2      |

|10 CFR SECTION:                                 |                             |

|ASHU 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   |

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

|3     N          Y       100      Power Operation  |0        Cold Shutdown    |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO ROD CONTROL SYSTEM ERROR    |

|                                                                              |

| "Shutdown Bank 'B' group step counter for group (1) did not indicate outward |

| rod motion during rod exercising surveillance.  Shutdown Bank 'B' group (2)  |

| step counter indicated normal outward rod motion.  Urgent failure for rod    |

| control system annunciator received.  Tech Specs required initiation of      |

| Nuclear Plant Shutdown."                                                     |

|                                                                              |

| At the time of this notification, the plant is in Mode 1 at 80% power with a |

| controlled plant shutdown in progress.  The licensee has notified the NRC    |

| Resident Inspector.                                                          |

|                                                                              |

| Notified R2DO (R. Haag)                                                      |

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



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

|Power Reactor                                    |Event Number:   39867       |

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

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

| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 05/20/2003|

|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 11:39[EDT]|

|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        05/20/2003|

+------------------------------------------------+EVENT TIME:        10:52[EDT]|

| NRC NOTIFIED BY:  JEFF GRANT                   |LAST UPDATE DATE:  05/20/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

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

|EMERGENCY CLASS:          NON EMERGENCY         |ROBERT HAAG          R2      |

|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   |

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

|3     N          Y       83       Power Operation  |83       Power Operation  |

|                                                   |                          |

|                                                   |                          |

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

                                   EVENT TEXT                                   

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

| EMERGENCY RESPONSE DATA SYSTEM UNABLE TO SUPPLY DATA TO NRC OPERATIONS       |

| CENTER                                                                       |

|                                                                              |

| "The Emergency Response Data System (ERDS) was discovered at 1022 [Et] to be |

| unable to supply ERDS data to the NRCOC.  At 1052, a loss of the ability to  |

| supply ERDS for greater than 30 minutes occurred.  This constitutes a        |

| reportable event based upon 10CFR50.72(b)(3)(xiii).                          |

|                                                                              |

| "At the time the failure was discovered, the Turkey Point Unit 3 was in the  |

| process of responding to a Technical Specifications required shutdown due to |

| a failure in the rod control system (reported separately). The anticipated   |

| unit condition will be Mode 3 until the rod control system is repaired."     |

|                                                                              |

| The licensee will notify the NRC Resident Inspector.  Notified R2DO (R.      |

| Haag)                                                                        |

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



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

|Fuel Cycle Facility                              |Event Number:   39869       |

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

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

| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 05/20/2003|

|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 23:46[EDT]|

| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/20/2003|

|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        09:30[EDT]|

|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/21/2003|

|    CITY:  PIKETON                  REGION:  3  +-----------------------------+

|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |

|LICENSE#:  GDP-2                 AGREEMENT:  N  |ANNE MARIE STONE     R3      |

|  DOCKET:  0707002                              |JOHN HICKEY          NMSS    |

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

| NRC NOTIFIED BY:  JIM McCLEERY                 |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|OSAF 76.120(c)(2)        SAFETY EQUIPMENT FAILUR|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

| SAFETY EQUIPMENT FAILURE                                                     |

|                                                                              |

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

|                                                                              |

| "05/20/03 at 0930 hrs. following the investigation into circumstances        |

| surrounding NRC Event #39853 (PTS-2003-011 update #1), the Plant Shift       |

| Superintendent's (PSS) office was notified that the air supply line to the   |

| parent cylinder safety valves had been disconnected during applicable TSR    |

| mode III (Cylinder/Pigtail Operations) on multiple occasions in both the     |

| X-343 and X-344 facilities.  Discussions with facility management and        |

| operating personnel indicate the air supply line was disconnected in         |

| preparation for sampling operations.  This condition is reportable under     |

| 76.120 (c)(2)(ii) and 76.120 (d)(2).  The equipment is required by Technical |

| Safety Requirements (TSR) to be available and operable and either should     |

| have been operating or have operated on demand.                              |

|                                                                              |

| "The PSS directed an extent of condition be performed for cylinder           |

| operations in X-342, X-343, X-344 and X-326 withdrawal station.  The result  |

| of the extent of condition placed the X-343 sample autoclaves in mode VII    |

| (shutdown) and removed from service until affected procedures can be         |

| changed, the X-344 autoclaves remain operable, the X-342 autoclaves remains  |

| inoperable, and the X-326 withdrawal station remains operable."              |

|                                                                              |

| The regulatee has notified the NRC Resident Inspector.                       |

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



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

|Fuel Cycle Facility                              |Event Number:   39870       |

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

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

| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 05/21/2003|

|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 00:08[EDT]|

| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        05/20/2003|

|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        19:15[CDT]|

|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  05/21/2003|

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

|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |

|LICENSE#:  GDP-1                 AGREEMENT:  Y  |ANNE MARIE STONE     R3      |

|  DOCKET:  0707001                              |JOHN HICKEY          NMSS    |

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

| NRC NOTIFIED BY:  C. PITTMAN                   |                             |

|  HQ OPS OFFICER:  HOWIE CROUCH                 |                             |

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

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NBNL                     RESPONSE-BULLETIN      |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

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



                                   EVENT TEXT                                   

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

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

|                                                                              |

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

|                                                                              |

| "At 1915 on 5/20/03, the Plant Shift Superintendent (PSS) was notified that  |

| some removed process gas equipment item groups in C-720 have not received    |

| proper independent mass verification in violation of NCSA GEN-010.  The      |

| group mass is required to be independently verified to be within always safe |

| mass limits.  This is done by independently verifying the equipment item     |

| mass is correctly copied onto the grouping sheet.  An entry was discovered   |

| on the grouping sheet in which the mass on the equipment was 0 [zero]        |

| pounds, however the GEN-010 tag on the equipment item indicated a mass of    |

| 284 pounds of uranium at 1.38% enrichment.  Additionally, several equipment  |

| items were tagged with GEN-010 tags that had information lined out and       |

| corrected, appearing to violate the independent verification of the          |

| equipment item mass, on the tag.  This information was then subsequently     |

| used for grouping purposes on the equipment grouping sheet. This is a legacy |

| issue, as the dates on the tags are from the 97-98 timeframe.                |

|                                                                              |

| "SAFETY SIGNIFICANCE OF EVENTS:                                              |

|                                                                              |

| "Double contingency was not maintained because the independent verification  |

| of mass has not been performed. However, the policy for the shop is to only  |

| allow items which have been fully decontaminated into the shop, which gives  |

| high confidence that less than a safe mass is present.                       |

|                                                                              |

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

| CRITICALITY COULD OCCUR):                                                    |

|                                                                              |

| "In order for a criticality to be possible, greater than a critical mass of  |

| uranium must be accumulated [and] then become moderated.                     |

|                                                                              |

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

|                                                                              |

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

|                                                                              |

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

| LIMIT AND %  WORST CASE CRITICAL MASS):                                      |

|                                                                              |

| "Less than an always safe mass of uranium.                                   |

|                                                                              |

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

| OF THE FAILURES OR DEFICIENCIES:                                             |

|                                                                              |

| "The first leg of double contingency is based on mass.  NCSA GEN-010         |

| requires that the total uranium mass of grouped items be verified less than  |

| the UH [Uncomplicated Handling] mass limit and documented.  The mass of an   |

| equipment item was incorrectly copied onto the grouping sheet.  However, the |

| listed mass for the item is UH at the listed enrichment.  In addition, other |

| items in the group have tags, which indicate no visible contamination but    |

| have been updated and only have one signature.  This mass was then used in   |

| the grouping.  The control was violated, however the parameter has been      |

| maintained.                                                                  |

|                                                                              |

| "The second leg of double contingency is based on mass.  NCSA GEN-010        |

| requires that the total uranium mass of grouped items be independently       |

| verified less than the UH mass limit and documented in accordance with       |

| CP2-PO-FO1031 [a facility procedure].  The independent verification was      |

| incorrectly performed; therefore, this control was violated.  Since there    |

| are two controls on one parameter, double contingency was not maintained.    |

|                                                                              |

| "Since double contingency is based on two controls on one parameter, and a   |

| control was violated, double contingency was not maintained.                 |

|                                                                              |

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

| IMPLEMENTED:                                                                 |

|                                                                              |

| "Ensure each item in the group is properly tagged according to CP2-CO-CN2030 |

| [a facility procedure].  Properly group and document each equipment item     |

| according to CP2-CO-CN2030.  Upon completion of the above corrective         |

| actions, the exclusion zone and postings may be removed."                    |

|                                                                              |

| The regulatee has notified the NRC Resident Inspector.                       |

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