United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2000

Event Notification Report for August 2, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           08/01/2000 - 08/02/2000

                              ** EVENT NUMBERS **

37166  37199  37201  37202  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37166       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 07/14/2000|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 14:55[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        07/14/2000|
+------------------------------------------------+EVENT TIME:        13:30[CDT]|
| NRC NOTIFIED BY:  JIM McKAY                    |LAST UPDATE DATE:  08/01/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE JORGENSEN      R3      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| VEHICLE ADMITTED TO THE PROTECTED AREA WITHOUT BEING COMPLETELY SEARCHED.    |
|                                                                              |
| The licensee admitted a new 2-ton truck to the protected area for use as a   |
| designated vehicle.  They discovered 23 hours after the truck had been       |
| admitted to the protected area, that two compartments on the truck had not   |
| been searched.  They were immediately searched with nothing found.           |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector and the state and  |
| local authorities.                                                           |
|                                                                              |
|                                                                              |
| * * * UPDATE AT 1240 ON 8/1/00,  BY CHRISTIAN RECEIVED BY WEAVER * * *       |
|                                                                              |
| This event has been retracted.  Upon further review it has been determined   |
| that this event does not fall into the reportable categories identified in   |
| NUREG 1304 or Generic Letter 91-03.  This event will continue to be tracked  |
| as a logable event.  The licensee will notify the NRC resident inspector.    |
| The Operations center notified the R3DO (Creed).                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37199       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 07/30/2000|
|    UNIT:  [] [2] []                 STATE:  AR |NOTIFICATION TIME: 18:39[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        07/30/2000|
+------------------------------------------------+EVENT TIME:        16:35[CDT]|
| NRC NOTIFIED BY:  TOM MOSBY                    |LAST UPDATE DATE:  08/01/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BILL JONES           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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INDICATION OF REACTOR COOLANT LEAKAGE ON PRESSURIZER HEATER PENETRATIONS     |
|                                                                              |
| "Boron was discovered on the reactor coolant system (RCS) pressurizer heater |
| power cables.  An inspection of the heater sleeves was performed and it      |
| appears that two heaters (B2 and D2) are leaking.  B2 is on backup heater    |
| bank #4 and D2 is on backup heater bank #6. The leakage appears to be the    |
| result of primary water stress corrosion cracking (PWSCC) of either the      |
| heater sleeve or the J-groove weld between the heater sleeve and the         |
| pressurizer cladding. The insulation will need to be removed to positively   |
| determine which heater sleeve(s) had been leaking.  Currently, Unit 2 is in  |
| reduced inventory with the pressurizer empty.  The pressurizer heater sleeve |
| penetrations were inspected during 2R-13 [between 1/9/99 and 2/25/99] as     |
| part of the routine I-600 inspections performed each refueling outage.  No   |
| indication of leakage was evident during that inspection.  Pressurizer       |
| heater sleeve leakage is considered RCS pressure boundary leakage."          |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 0052 ON 07/31/00 BY LARRY McLERRAN TO JOLLIFFE * * *         |
|                                                                              |
| After removing insulation from the pressurizer and RCS hot legs, the         |
| licensee discovered 9 or 10 additional pressurizer heater sleeves that are   |
| leaking and also a hot leg temperature element (TE) that is leaking.  The    |
| licensee is continuing to inspect the hot leg penetrations for evidence of   |
| leakage.                                                                     |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The NRC Operations        |
| Officer notified R4DO Bill Jones.                                            |
|                                                                              |
| * * * UPDATE AT 0829 ON 07/31/00 BY WAYNE AHO TO JOLLIFFE * * *              |
|                                                                              |
| The licensee discovered indications on RCS hot leg TE #2TE-4710-3 that is    |
| indicative of a  RCS pressure boundary leak.  The TE is installed above the  |
| water line in the 'B' hot leg on the reactor coolant pump #2P-32C side.  The |
| licensee is continuing to inspect the hot leg penetrations for evidence of   |
| leakage.                                                                     |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.  The NRC Operations |
| Officer notified R4DO Bill Jones.                                            |
|                                                                              |
| *** UPDATE/PARTIAL RETRACTION AT 1047 ON 08/01/00 FROM WAYNE AHO TO BOB      |
| STRANSKY ***                                                                 |
|                                                                              |
| The licensee is retracting the last update.  The following text is a portion |
| of a facsimile received from the licensee:                                   |
|                                                                              |
| "This information is provided as an update to Event #37199, and applies only |
| to the update given on 07/31/00 at 0829 EDST, and only to the RCS boundary   |
| at the nozzle for 2TE-4710-3.                                                |
|                                                                              |
| "The remaining information in Event #37199 remains correct at this time.     |
|                                                                              |
| "The nozzle for 2TE-4710-3 was re-inspected, and there was a very fine ring  |
| of white material immediately around the nozzle penetration into the         |
| hot-leg.  No indication of leakage was observed down the side of the hot-leg |
| pipe.  Chemistry personnel took a small sample of the white material for     |
| analysis.  The results of the analysis was conclusive that the white         |
| material was not boron.  Because of the location of the white material and   |
| the results of the chemistry analysis, it is concluded there is high         |
| confidence that 2TE-4710-3 is not leaking around this nozzle.                |
|                                                                              |
| "The source of the white ring was from a Component Cooling Water (CCW)       |
| leaking flange located above the TE-4710-3 nozzle."                          |
|                                                                              |
| The NRC operations officer notified the R4DO (Spitzberg).                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37201       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 08/01/2000|
|    UNIT:  [3] [4] []                STATE:  FL |NOTIFICATION TIME: 10:44[EDT]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        08/01/2000|
+------------------------------------------------+EVENT TIME:        10:20[EDT]|
| NRC NOTIFIED BY:  PAUL REIMERS                 |LAST UPDATE DATE:  08/01/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |STEPHEN CAHILL       R2      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|4     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - CARM ISOLATION VALVES LABELS IN CONTROL ROOM DIFFERENT THAN UFSAR          |
| DESCRIPTION -                                                                |
|                                                                              |
| Tables 7.5-1 and 7.5-2 of the Turkey Point UFSAR indicate that "Open/Close"  |
| position indication is provided in the control room for the containment      |
| atmosphere radiation monitor (CARM) isolation valves #SV-*-2911, #SV-*-2912  |
| and #SV-*-2913 (containment isolation valves) in compliance with commitments |
| related to NRC Reg Guide 1.97 (Revision 3).  Contrary to this, the stated    |
| containment isolation valves are provided with "Open/Not Open" position      |
| indication in the control room.                                              |
|                                                                              |
| Tech Spec LCO 3.3.3.3, Action 39 requires the licensee to restore the valves |
| to operable status within 72 hours or isolate the related containment        |
| penetrations within 4 hours in accordance with Tech Spec 3.6.4.              |
|                                                                              |
| Since the installed configuration does not meet the plant design as          |
| described in the UFSAR, the condition is considered to be reportable under   |
| the requirement of 10 CFR 50.72(b)(1)(ii)(B) as a condition that is outside  |
| the plant design basis.                                                      |
|                                                                              |
| The licensee is determining corrective actions.                              |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37202       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 08/01/2000|
|    UNIT:  [2] [3] []                STATE:  PA |NOTIFICATION TIME: 19:06[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        08/01/2000|
+------------------------------------------------+EVENT TIME:        18:47[EDT]|
| NRC NOTIFIED BY:  BREIDENBAUGH                 |LAST UPDATE DATE:  08/01/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK MCFADDEN        R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       93       Power Operation  |93       Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS - EDG COOLING WATER                                     |
|                                                                              |
| This report is being made pursuant to 10CFR50.72(b)(1)(ii) due to the plant  |
| being in a condition outside the design basis.  During initial analysis of   |
| data acquired from the Emergency Diesel Generator (EDG) GL 89-13 testing, it |
| has been determined that cross flow exists between the jacket water and air  |
| cooler loops on the EDGs. As a result, the air cooler heat exchanger         |
| capacity may be exceeded during a LOCA / LOOP condition when heat sink       |
| temperature is greater than approximately 80F.   Previous hot weather       |
| conditions during the summer of 1999 and early 2000 resulted in heat sink    |
| temperatures being greater than 80F for several days.  Currently, heat sink |
| temperatures are below 80F.  The EDGs are currently operable, further       |
| analysis is being conducted to increase margin, and compensatory actions are |
| being developed to reduce cross flow between heat exchangers.                |
|                                                                              |
| The NRC resident has been notified.                                          |
+------------------------------------------------------------------------------+