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 |
| | |
| | |
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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 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 !!!!!!!
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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: 02/16/2000|
| 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
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| 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 |
+------------------------------------------------------------------------------+
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| 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
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| 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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|Power Reactor |Event Number: 36698 |
+------------------------------------------------------------------------------+
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| 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
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| 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 |
+------------------------------------------------------------------------------+
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| 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 | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| 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. |
+------------------------------------------------------------------------------+
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|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. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021