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Event Notification Report for February 17, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/16/2000 - 02/17/2000

                              ** EVENT NUMBERS **

36695  36696  36697  36698  36699  36700  

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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:  02/16/2000|
|  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     |
|NOCM                     COMM ASST BRIEF        |DUTY  OFFICER        FEMA    |
|                                                |WYATT                DOE     |
|                                                |CONLEY               USDA    |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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 indication of a steam       |
| generator tube rupture on steam generator #24. The steam generator tube      |
| rupture was initially estimated to be approximately 90 gallons per minute.   |
| At 1929, 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 at 1929 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.       |
|                                                                              |
| * * * UPDATE AT 1000 @2/16/00 * * * COMMISSIONER'S ASSISTANTS BRIEFING GIVEN |
| BY RANDY BLOUGH ON THE INDIAN PT 2  ALERT.                                   |
|                                                                              |
| The following persons participated in the briefing:  Region 1 RA (Hub        |
| Miller), R1 PAO(Diane Screnci),  R1 (Jennifer England), RI (Pete             |
| Habighorst),  R1DO (F. Costello),  IRO (F. Congel), EDO (Bill Travers), DEDR |
| (Frank Miraglia), NRR (Sam Collins), EDO Staff (Mike Tschiltz),  Chairman's  |
| Office (Terence Chan), Comm. Dicus' (Thomas Hiltz), Comm. McGaffigan's (Jeff |
| Sharkey), Comm. Diaz's (Roger Davis), Comm. Merrifield's (Brain McCabe),     |
| NRR PD (Jim  Clifford), PM (Jeff Harold), NRR EO (Tad Marsh),  PA (Sue       |
| Gagner), State Programs (Paul Lohaus),  IP (Howard Faulkner),  and CAO (Tom  |
| Madden). DEDMRS Staff and SECY did not participate.                          |
|                                                                              |
| * * * UPDATE AT 1922 @ 2/16/00 BY SPALL TAKEN BY MACKINNON * * *             |
|                                                                              |
| As of 1657 hours, Unit 2 attained a cold shutdown condition. Leakage from    |
| the reactor coolant system into # 24 steam generator has stopped.  Indian    |
| Point 2 is terminating the alert classification as of 1850 hours and will be |
| entering the Recovery Phase.                                                 |
|                                                                              |
|                                                                              |
| At 1915 hours NRC exited Monitoring mode and returned to normal operations.  |
|                                                                              |
| NRC Resident Inspectors notified.                                            |
|                                                                              |
| R1DO (F Costello), NRR EO(D Wessman) and IRO (Joe Giitter) notified.         |
|                                                                              |
| FEMA (Eaches), DOE (Bob Young), USDA (Corley), HHS (Pamela), and EPA         |
| (Garneau) notified that Indian Point Unit 2 exited their Alert               |
| classification at 1850 hour and entered Recovery Phase and were also         |
| notified that the Nuclear Regulatory Commission exited Monitoring Mode at    |
| 1915 hours.                                                                  |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36696       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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:  02/16/2000|
|  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  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   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.                            |
|                                                                              |
| * * * RETRACTION ON 02/16/00 AT 1647ET BY S. SAUER TAKEN BY MACKINNON * * *  |
|                                                                              |
| Further review of the above event report for reactor coolant leakage outside |
| containment, which may have resulted in exceeding GDC-19 criteria for        |
| control room habitability has identified that this leakage flow path is not  |
| part of the post accident recirculation flow path in communication with the  |
| containment sump.  Leakage from systems that are isolated from the           |
| recirculation flow path or that can be isolated from it, without degrading   |
| the ability to recirculate the reactor coolant system are not included in    |
| leakage requirement of the USFAR.                                            |
| R1DO (F. Costello) notified.                                                 |
|                                                                              |
| The NRC Resident inspector was notified of this event retraction by the      |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36698       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 02/16/2000|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 14:41[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        02/16/2000|
+------------------------------------------------+EVENT TIME:        13:52[EST]|
| NRC NOTIFIED BY:  REGIS REPKO                  |LAST UPDATE DATE:  02/16/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KENNETH BARR         R2      |
|10 CFR SECTION:                                 |JIM LYONS            NRR     |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |CHARLIE MILLER       IRO     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |80       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO AN UNISOLABLE REACTOR       |
| COOLANT PRESSURE BOUNDARY LEAKAGE.                                           |
|                                                                              |
| At 1305 EST on 02/16/00 a small leak ("weeping steam") was discovered in the |
| reactor coolant system pressure boundary on a 1.5 inch (ID) post accident    |
| sampling system line.  The leak is estimated to be 0.03 gpm based on         |
| historical trending of the reactor building normal sump.  The leak was       |
| discovered during a reactor building entry to investigate reactor coolant    |
| pump seal indications.                                                       |
|                                                                              |
| At 1352 EST on 02/16/00 shutdown was commenced.  Unit 1 must be in Mode 3    |
| (Hot Standby) by 02/17/00 at 0105 EST and in Mode 5 (Cold Shutdown) by       |
| 02/18/00 at 0105 EST per Technical Specification 3.4.13, "Reactor Coolant    |
| Operational Leakage."                                                        |
|                                                                              |
| The post accident sampling line connects to the coolant cold leg piping      |
| between the "B" once through steam generator and the suction side of reactor |
| coolant pump "1B2". The leak is coming from the area of a 90 degree elbow    |
| where the sampling line passes near the containment floor.                   |
|                                                                              |
| All emergency core cooling systems and the Keowee system are fully operable. |
| The electrical grid is also stable.                                          |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   36699       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ONCOLOGY INST. OF GREATER LAFAYETTE  |NOTIFICATION DATE: 02/16/2000|
|LICENSEE:  ONCOLOGY INST. OF GREATER LAFAYETTE  |NOTIFICATION TIME: 16:12[EST]|
|    CITY:  LAFAYETTE                REGION:  3  |EVENT DATE:        02/16/2000|
|  COUNTY:  TIPPECANOE                STATE:  IN |EVENT TIME:        15:00[CST]|
|LICENSE#:  13-32087-01           AGREEMENT:  N  |LAST UPDATE DATE:  02/16/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BRUCE JORGENSEN      R3      |
|                                                |ROBERT PIERSON       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  Dr. CHANG                    |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNINTENDED SITE IRRADIATED                                                   |
|                                                                              |
| While performing high dose rate (HDR) endobronchial brachytherapy, it was    |
| discovered that unintended sites in a patient had been irradiated.  The      |
| licensee uses a Nulceatron Micro Selection HDR #31024, controlled by an IBM  |
| G50 computer. It was discovered that after the dwell time was entered into   |
| the computer, if the enter key is pushed twice instead of once, the distance |
| that the source moves is increased by 100% without warning the operator that |
| the distance had changed. (If the source is supposed move 4 centimeters and  |
| you push the enter key twice that source will move 8 centimeters). A patient |
| received three unintended site radiation treatments to his bronchial tube    |
| before the problem was discovered.  An NRC Region 3 Inspector was at the     |
| facility when this incident occurred.                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36700       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 02/16/2000|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 19:19[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        02/16/2000|
+------------------------------------------------+EVENT TIME:        17:55[CST]|
| NRC NOTIFIED BY:  J SELL                       |LAST UPDATE DATE:  02/16/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE JORGENSEN      R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TEMPORARY FIRE PENETRATION IN THE CABLE SPREADING ROOM WAS FOUND TO BE       |
| POTENTAILLY OUTSIDE THE PLANTS DESIGN BASIS.                                 |
|                                                                              |
| A condition was discovered which is potentially outside the plants design    |
| basis.  Engineering review of a temporary fire penetration in the cable      |
| spreading room determined that it would not withstand a high energy line     |
| break event.  This may result in the temperature in the cable spreading room |
| exceeding the design basis temperature for equipment located in the room.    |
| The temporary fire penetration has been sealed and is now fully operable.    |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+