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Event Notification Report for February 16, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/15/2000 - 02/16/2000

                              ** EVENT NUMBERS **

36692  36694  36695  36696  36697  

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|Fuel Cycle Facility                              |Event Number:   36692       |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 02/15/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 00:30[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/14/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        17:00[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  02/15/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |BRUCE JORGENSEN      R3      |
|  DOCKET:  0707002                              |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM McCLEERY                 |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| 24-HOUR NRC BULLETIN 91-01 REPORT INVOLVING LOSS OF GEOMETRY/VOLUME          |
| CRITICALITY CONTROL IN THE X-705 DECONTAMINATION FACILITY                    |
|                                                                              |
| "On 2/14/00 the Plant Shift Superintendent (PSS) was notified of the loss of |
| one control parameter, geometry/volume in the X-705 decontamination          |
| facility. A vinyl covered foam padded chair was found in the high bay area   |
| with the vinyl covering worn open. This is a violation of NSCA-0705_076      |
| inadvertent containers. The foam padding thickness was greater than the      |
| requirement for absorbent material described in NCSA-0705_076.               |
|                                                                              |
| "The system integrity of nearby uranium-bearing pipes was maintained.        |
| Therefore, no solution was actually present to accumulate on/in the padding  |
| of the chair.                                                                |
|                                                                              |
| "The chair was moved to an area in the high bay not covered by the above     |
| described NCSA. Compliance with NCSA--0705_076 is restored                   |
|                                                                              |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                      |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT.   |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:                                              |
|                                                                              |
| "A padded chair (seat dimensions approximately 17.5" x 21" x 3.5") was used  |
| near a uranium solution transfer line. The vinyl on the seat was damaged to  |
| the point that any solution if splashed in to the chair could have           |
| accumulated in the padding. The padding is an unsafe height > 1 .5") and has |
| a total volume >20 liters, which is well above the allowed limit of 4.8      |
| liters. The transfer line near this seat can contain high concentrations of  |
| HEU solution.                                                                |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW           |
| CRITICALITY COULD OCCUR):                                                    |
|                                                                              |
| "If the solution line had failed, uranium-bearing solution could have        |
| splashed/sprayed onto the seat padding and accumulated. Since the total      |
| volume of the padding was greater than the allowed 4.8 liters and the height |
| (excluding and swelling of the material) was greater than the allowed 1.5"   |
| an unsafe condition would have resulted and a criticality could have         |
| resulted.                                                                    |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION. GEOMETRY, CONCENTRATION, ETC.):    |
|                                                                              |
| The parameter lost was the geometry/volume of the absorbent material on the  |
| chair. The physical integrity of the transfer line was maintained.           |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS    |
| LIMIT AND % WORST                                                            |
|                                                                              |
| "No material accumulated on/in the chair padding. The transfer line near the |
| chair can contain HEU solutions with high uranium concentrations.            |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES                                              |
|                                                                              |
| "Requirement #4 requires that absorbent material be covered or modified to   |
| prevent an unfavorable accumulation in the event of a solution leak in a     |
| nearby system. The chair padding was absorbent and the vinyl covering had    |
| degraded to the point that solution hitting the chair could accumulate in    |
| the padding.                                                                 |
|                                                                              |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:  |
|                                                                              |
| "Compliance was regained when the chair was moved to an area not covered by  |
| NCSA-0705_076. Crew briefing are being conducted shiftily and the chair in   |
| question is caution boundaried."                                             |
|                                                                              |
| Operations personnel notified both the DOE Site Representative and the NRC   |
| Resident Inspector.                                                          |
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|Other Nuclear Material                           |Event Number:   36694       |
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| REP ORG:  INEEL                                |NOTIFICATION DATE: 02/15/2000|
|LICENSEE:  THREE MILE ISLAND - UNIT 2           |NOTIFICATION TIME: 17:36[EST]|
|    CITY:  IDAHO FALLS              REGION:  4  |EVENT DATE:        02/15/2000|
|  COUNTY:                            STATE:  ID |EVENT TIME:        13:25[MST]|
|LICENSE#:  SNM-2508              AGREEMENT:  N  |LAST UPDATE DATE:  02/15/2000|
|  DOCKET:  72-20                                |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN PELLET          R4      |
|                                                |ROBERT PIERSON       NMSS    |
+------------------------------------------------+RICHARD WESSMAN      NRR     |
| NRC NOTIFIED BY:  JAMES E. KAYLOR              |JOSEPH GIITTER       IRO     |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|ISFS 72.75               SPENT FUEL CASK EVENT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| THREE MILE ISLAND UNIT 2 SPENT FUEL STORAGE CONFINEMENT SYSTEM IN USE HAS A  |
| POTENTIAL FOR A SIGNIFICANT REDUCTION IN EFFECTIVENESS.  THIS IS NOT A       |
| SAFETY ISSUE.                                                                |
|                                                                              |
|                                                                              |
| At 1325 MST, 15 FEB 2000,  a determination was made that a spent fuel        |
| storage confinement system in use has a potential for a significant          |
| reduction in effectiveness.                                                  |
|                                                                              |
| This conclusion is based on an engineering evaluation of plugs in the Three  |
| Mile Island Unit 2 (TMI-2) core debris Canisters.  These plugs are           |
| approximately 2" diameter and there are two plugs in each TMI-2 Canister.    |
| There are eight TMI-2 Canisters in the Dry Storage Canister (DSC) currently  |
| in storage at the TMI-2 ISFSI.  The TMI-2 ISFSI Safety Analysis Report takes |
| credit for the plugs being in place for the design function of the           |
| confinement of radioactive material.                                         |
|                                                                              |
| The DSC containing the eight TMI-2 Canisters continues to provide an intact  |
| outer confinement boundary.                                                  |
|                                                                              |
| The condition described above exists at the TMI-2 ISFSI at the Idaho         |
| National Engineering and Environmental Laboratory.                           |
|                                                                              |
| The affected DSC contains eight TMI-2 Canisters containing TMI-2 core        |
| debris.  The U-235 inventory is conservatively estimated to be significantly |
| less than 1 kilogram for the entire DSC.                                     |
|                                                                              |
| There are no potential for personnel radiation exposure associated with this |
| condition.  There is no potential for release of radioactive material from   |
| the DSC associated with this condition.                                      |
|                                                                              |
| NRC Region IV has been notified of this event.                               |
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|Power Reactor                                    |Event Number:   36695       |
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| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 02/15/2000|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 20:07[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        02/15/2000|
+------------------------------------------------+EVENT TIME:        19:29[EST]|
| NRC NOTIFIED BY:  TOWNDSON                     |LAST UPDATE DATE:  02/15/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          ALE                   |FRANK COSTELLO       R1      |
|10 CFR SECTION:                                 |RICHARD WESSMAN      NRR     |
|AAEC 50.72 (a) (1) (I)   EMERGENCY DECLARED     |JOSEPH GIITTER       IRO     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     M/R        Y       99       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| REACTOR MANUALLY TRIPPED DUE TO INDICATION OF A STEAM GENERATOR TUBE RUPTURE |
| ON STEAM GENERATOR # 24.                                                     |
|                                                                              |
| The licensee was at 99% power when they received a nitrogen-16 alarm on the  |
| main steam and other indication of a Steam Generator Tube Rupture on Steam   |
| Generator # 24. Initial Steam Generator Tube Rupture was initially estimated |
| at greater than 75 gallons per minute.  The reactor was manually tripped and |
| all rods fully inserted into the core.  The faulted Steam Generator was      |
| isolated. Currently reactor coolant system pressure is 2243 psig,            |
| temperature is 547 F and pressurizer level is being maintained at 35%. The  |
| licensee declared an Alert classification per EAL 3.1.2 (large amount of     |
| water out of the reactor coolant system). The NRC entered Standby at 2049    |
| EST.                                                                         |
|                                                                              |
| The NRC response was deescalated to Monitoring at 2335 EST.                  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36696       |
+------------------------------------------------------------------------------+
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| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 02/15/2000|
|    UNIT:  [] [2] []                 STATE:  NJ |NOTIFICATION TIME: 20:35[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        02/15/2000|
+------------------------------------------------+EVENT TIME:        19:40[EST]|
| NRC NOTIFIED BY:  SUE SIMPSON                  |LAST UPDATE DATE:  02/15/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |FRANK COSTELLO       R1      |
|10 CFR SECTION:                                 |RICHARD WESSMAN      NRR     |
|ADEG 50.72(b)(1)(ii)     DEGRAD COND DURING OP  |JOSEPH GIITTER       IRO     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIDENTIFIED LEAKAGE 1.1 GALLONS PER MINUTE                                  |
|                                                                              |
| "Elevated reading noted on Unit 2 Plant Vent Radiation Monitor (2R41D)       |
| concurrent with slowly lowering Volume Control Tank (VCT) level.  Plant was  |
| operating at 100% reactor power.  Investigation by on-shift personnel        |
| estimated unidentified RCS leakage at 1.1 gpm.  This value exceeds the Tech  |
| Spec limit of 1 gpm unidentified (Reference Tech Spec 3.4.7.2).  The Unit 2  |
| Reactor Coolant Filter had been replaced on dayshift.  Operators isolated    |
| the Reactor Coolant Filter at 2010 and the leakage appears to be stopped.    |
| This report is being made for RCS leakage outside containment which may      |
| result in exceeding GDC-19 criteria for Control Room habitability."          |
|                                                                              |
| The leak appears to have started at 1638 EST and was stopped at 2010 EST.    |
| The volume that was lost is estimated at 160 gallons, the leak was through a |
| hard pipe directly to a radiation waste tank.                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36697       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 02/16/2000|
|    UNIT:  [1] [] []                 STATE:  AR |NOTIFICATION TIME: 00:21[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        02/15/2000|
+------------------------------------------------+EVENT TIME:        20:58[CST]|
| NRC NOTIFIED BY:  PHILLIP REHM                 |LAST UPDATE DATE:  02/16/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN PELLET          R4      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FLAWED WELD DISCOVERED DURING PLANT OUTAGE                                   |
|                                                                              |
| "At 2058 CST on 2/15/2000, a flawed weld was identified on an instrument     |
| connection to the Reactor Coolant System Loop 'A' Hot Leg Piping. The        |
| subject flaw was identified by Non-Destructive Examination (NDE) at the      |
| connection of Level Instrumentation to the RCS Hot Leg Piping.               |
|                                                                              |
| "Unit 1 was taken offline at 0010 on 2/5/2000 for scheduled maintenance.     |
| Boron buildup was identified on 2/15/00 at the subject connection while the  |
| plant was at cold shutdown condition. The accumulated boron indicates the    |
| leakage through the weld flaw is classified as very small weepage. The       |
| unidentified RCS leakrate prior to thc scheduled outage was 0.093 GPM. No    |
| unexplainable changes in RCS leakrate exist for cycle 16 operation. Due to   |
| the physical location of the connection, major scaffolding was required to   |
| access the area. At 2058 on 2/15/2000, NDE was complete identifying the      |
| reportable condition. Further investigation by Plant Staff is in-progress to |
| characterize the flaw morphology and cause.                                  |
|                                                                              |
| "This report is being performed to comply with the requirements of           |
| 10CFR50.72(b)(2)(i)."                                                        |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
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