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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