Event Notification Report for November 2, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/01/2001 - 11/02/2001
** EVENT NUMBERS **
38435 38453 38454 38457
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|Power Reactor |Event Number: 38435 |
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| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 10/28/2001|
| UNIT: [1] [] [] STATE: VA |NOTIFICATION TIME: 01:05[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/28/2001|
+------------------------------------------------+EVENT TIME: 00:15[EDT]|
| NRC NOTIFIED BY: ALLEN HARROW |LAST UPDATE DATE: 11/02/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BOB HAAG, REGION 2 IRC |
|10 CFR SECTION: |WILLIAM BECKNER NRR |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| DISCOVERY OF APPARENT THROUGH-WALL INDICATIONS ON CONTROL ROD DRIVE
|
| MECHANISM PENETRATIONS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "Following shutdown for a scheduled refueling outage, Surry Unit 1 performed |
| a visual inspection of the reactor vessel control rod drive mechanism (CRDM) |
| penetrations per NRC Bulletin 2001-01." |
| |
| "At approximately 0015 on October 28, 2001, apparent through-wall |
| indications were identified on CRDM penetrations 27 and 40. The inspection |
| is not yet complete. This condition did not pose a significant safety risk |
| during plant operation. This is being reported as a non-emergency (8-hour |
| report in accordance with 10 CFR 50.72(b)(3)(ii)(A) and |
| 50.73(a)(2)(ii)(A)." |
| |
| The licensee stated that the unit is currently defueled. |
| |
| The licensee notified the NRC resident inspector. |
| |
| * * * UPDATE ON 11/2/01 @ 0338 BY HILBERT-SEMMES TO GOULD * * * UPDATE |
| |
| Following shutdown for a scheduled refueling outage, Surry Unit 1 performed |
| a visual inspection of the reactor vessel Control Rod Drive Mechanism (CRDM) |
| penetrations per NRC Bulletin 2001-01. |
| |
| At approximately 0220 hours on November 2, 2001, additional indications were |
| identified as having flaws that are not acceptable under ASME Section XI |
| IWB-3600 on penetrations 65, 47, and 69. Two previously identified |
| indications were previously reported in this event. The inspection of all |
| CRDM penetrations is now complete with disposition of one penetration still |
| underway. This condition did not pose a significant safety risk during |
| plant operation. This is being reported as an update. |
| |
| The NRC Resident Inspector was notified. The Reg 2 IRC Manager was |
| notified. |
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|Power Reactor |Event Number: 38453 |
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| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 11/01/2001|
| UNIT: [1] [] [] STATE: AL |NOTIFICATION TIME: 09:47[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/31/2001|
+------------------------------------------------+EVENT TIME: [CST]|
| NRC NOTIFIED BY: HAWKINS |LAST UPDATE DATE: 11/01/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |R2 IRC TEAM MANAGER R2 |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Standby |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| CONTROL RODS DID NOT FULLY INSERT DURING CONTROL ROD TEST |
| |
| On October 31 and November 1, 2001 following reactor vessel assembly and |
| heat up, control rod drop testing was performed in mode 3. Rods N-9 and C-9 |
| did not fully insert into the dashpot region (24 steps) following |
| operability and trip testing. Rod J-13 exhibited similar characteristics |
| following operability and trip testing but shortly after trip testing it |
| fully inserted. Four other rods fully inserted but were slower than normal |
| in the dashpot region. All other control rods tested fully acceptable. The |
| Unit is currently cooling down and plans are under way to replace |
| unacceptable control rods as necessary. The Unit has remained borated above |
| the all rods out critical boron concentration since core reload and adequate |
| SDM exits. |
| |
| On October 06, 2001 Farley Unit 1 commenced a normal Unit shutdown to start |
| its 17th refueling outage. All control rods were fully inserted with no |
| problems. During insert and control rod changeout in the Unit 1 fuel pool |
| several control rods not scheduled to go back into the core experienced |
| binding in older fuel assemblies that prevented the rods from fully |
| inserting in the dashpot region of assemblies. Upon investigation of the |
| old control rods scheduled to be replaced axial cracks were observed by |
| visual exmination in several assemblies near the rod ends but above the rod |
| tips. This resulted in an inspection program for 18 older control rods |
| scheduled to go back into the core to confirm the acceptability for |
| continued use in cycle 18. Visual inspection and drag testing was performed |
| in the Unit 1 Spent Fuel. Westinghouse reviewed the test results and |
| confirmed the acceptability of 18 control rods for Cycle 18 use. |
| |
| The NRC Resident was notified. |
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|Hospital |Event Number: 38454 |
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| REP ORG: ST BARNABAS MEDICAL CENTER |NOTIFICATION DATE: 11/01/2001|
|LICENSEE: ST BARNABAS MEDICAL CENTER |NOTIFICATION TIME: 10:36[EST]|
| CITY: LIVINGSTON REGION: 1 |EVENT DATE: 10/26/2001|
| COUNTY: STATE: NJ |EVENT TIME: [EST]|
|LICENSE#: 29-01608-03 AGREEMENT: N |LAST UPDATE DATE: 11/01/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |R1 IRC TEAM MANAGER R1 |
| |FRED BROWN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: GARELICK | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| MEDICAL MISADMINISTRATION DURING THERAPEUTIC TREATMENT REPORTED BY ST
|
| BARNABAS MEDICAL CENTER |
| |
| A patient undergoing the third therapeutic treatment received a dose to an |
| unintended treatment site due to an incorrect step size on a High Rate |
| Remote After Loader which was used in the treatment. This was the result of |
| human error. It was determined there will be no medical implications and |
| the patient will be notified. |
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|Power Reactor |Event Number: 38457 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 11/01/2001|
| UNIT: [] [2] [] STATE: AR |NOTIFICATION TIME: 15:13[EST]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 11/01/2001|
+------------------------------------------------+EVENT TIME: 12:30[CST]|
| NRC NOTIFIED BY: ALAN SMITH |LAST UPDATE DATE: 11/01/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |BLAIR SPITZBERG R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 22 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DURING CEA TROUBLESHOOTING FOR REASONS
UNKNOWN |
| |
| "While operating at full power at approximately 1010 CST on 11/01/2001, |
| Control Element Assembly (CEA) 43 dropped into the core for unknown reasons. |
| Reduction of reactor power began at approximately 1017. With reactor power |
| stable at approximately 22 percent, troubleshooting of the cause of the |
| CEA-43 drop was in progress at approximately 1230 CST when an automatic |
| reactor trip occurred. The reason for the trip is unknown. Plant response |
| to the trip was normal and uncomplicated. All CEAs fully inserted. There |
| were no ESF system actuations. The plant is stable in Hot Standby (Mode 3) |
| conditions with decay heat being removed via the Steam Generators to the |
| Main Condenser. No radiation releases occurred." |
| |
| The licensee informed the state and NRC Resident Inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021