Event Notification Report for February 28, 2003
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/27/2003 - 02/28/2003
** EVENT NUMBERS **
39613 39615 39623 39624 39625
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|General Information or Other |Event Number: 39613 |
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| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 02/24/2003|
|LICENSEE: SPECTRO ANALYTICAL INSTRUMENTS |NOTIFICATION TIME: 12:06[EST]|
| CITY: MARBLE FALLS REGION: 4 |EVENT DATE: 02/13/2003|
| COUNTY: STATE: TX |EVENT TIME: [CST]|
|LICENSE#: L-02788-003 AGREEMENT: Y |LAST UPDATE DATE: 02/24/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DAVID GRAVES R4 |
| |DOUG BROADDUS NMSS |
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| NRC NOTIFIED BY: JIM OGDEN | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
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EVENT TEXT
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| AGREEMENT STATE REPORT - LEAKING SEALED SOURCE |
| |
| The following information was obtained from the Texas Department of Health |
| via facsimile: |
| |
| "During routine service of an ASOMA (SPECTRO) Model 200, Serial No 4390, a |
| wipe test was performed on a 20 millicurie Am-241 source, Serial No 13730W. |
| Contamination of 0.035 microcuries was detected on the wipe. The source is |
| an AEA Technology (Amersham) Model AMC.D2 with a source product code |
| AMCK2175. It is encapsulated in an X10/2 capsule. The source was removed |
| and is being returned to the manufacturer for evaluation. All other |
| interior components and exterior surfaces of the instrument were wipe tested |
| and found to have no contamination above the Licensee's minimum detection |
| limit of 360 picocuries. Agency was notified by telephone of the leaking |
| source on February 13, 2003. A written report was sent to this Agency that |
| same date. This incident was closed February 24, 2003. No violations have |
| been cited. |
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|General Information or Other |Event Number: 39615 |
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| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 02/24/2003|
|LICENSEE: SPECTRO ANALYTIC INSTRUMENTS |NOTIFICATION TIME: 16:46[EST]|
| CITY: MARBLE FALLS REGION: 4 |EVENT DATE: 02/24/2003|
| COUNTY: STATE: TX |EVENT TIME: 14:00[CST]|
|LICENSE#: L-02788-003 AGREEMENT: Y |LAST UPDATE DATE: 02/24/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DAVID GRAVES R4 |
| |ROBERT PIERSON NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM OGDEN | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
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EVENT TEXT
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| AGREEMENT STATE REPORT - LEAKING SEALED SOURCE |
| |
| The following information was obtained from the Texas Department of Health |
| via facsimile: |
| |
| "Leaking source was discovered during routine servicing of an ASOMA Model |
| 200 analytical instrument, Serial No 4668. The instrument contained a sealed |
| Amersham 13 millicurie, Cm-244 source, Serial No 2695LM, Amersham Model No. |
| CLCL. Last assay date was 08/15/95. Leakage detected was from a routine |
| wipe test which resulted in 0.0077 microcuries of removable contamination. |
| The source is being prepared for return to the manufacturer for evaluation |
| and disposal. All other interior components and exterior surfaces of the |
| instrument were wipe tested and found to have no contamination above the |
| Licensee's minimum detection limit of 360 picocuries." |
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|Power Reactor |Event Number: 39623 |
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| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 02/27/2003|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 17:15[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/27/2003|
+------------------------------------------------+EVENT TIME: 13:01[EST]|
| NRC NOTIFIED BY: PETE SENA |LAST UPDATE DATE: 02/27/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN KINNEMAN R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
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| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 58 Power Operation |43 Power Operation |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC ACTUATION OF THE #2 EMERGENCY DIESEL GENERATOR |
| |
| "This provides notification of an automatic actuation of the No. 2 Emergency |
| Diesel Generator (EDG) at Beaver Valley Power Station (BVPS) Unit No. 1 |
| |
| "On 2/27/2003 at 1301 hours, BVPS Unit No. 1 was at 58 % power following a |
| startup from a recent forced outage. The 'B' Main Feedwater Pump (MFP) |
| tripped on overcurrent shortly after it was started. Concurrent with the MFP |
| trip, the breaker which feeds the non-safety related 'D' bus from the |
| offsite power source also tripped, de-energizing the 'D' bus. [The 'D' bus |
| supplies power to the 'B' MFP.] The loss of the 'D' bus caused the loss of |
| power to the safety related Emergency 'DF' bus, which caused the No. 2 EDG |
| to start and re-energize the Emergency 'DF' bus with all equipment properly |
| loaded. |
| |
| "Control Room personnel entered Abnormal Operating Procedure 1.36.2, 'Loss |
| of 4KV Emergency Bus.' Reactor Power was manually ramped back to 43 % power |
| in response to this transient. Actions are being taken to re-energize the |
| non-safety related 'D' bus from its offsite source. The EDG remains in |
| operation with no abnormalities. The cause of the 'B' MFP trip is being |
| investigated. |
| |
| "This condition is being reported pursuant to 10 CFR 50.72(b)(3)(iv)(A) as |
| an actuation of an emergency diesel generator which is part of the onsite |
| emergency AC electrical power system. The NRC resident has been notified." |
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|Power Reactor |Event Number: 39624 |
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| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 02/27/2003|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 19:50[EST]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 02/27/2003|
+------------------------------------------------+EVENT TIME: 17:31[CST]|
| NRC NOTIFIED BY: RANDY HASTINGS |LAST UPDATE DATE: 02/27/2003|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |THOMAS KOZAK R3 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |92 Power Operation |
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EVENT TEXT
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| PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS |
| |
| "On 02/27/03 at 1731[CST] hours, Point Beach Unit 1 commenced an orderly |
| reactor shutdown in response to TS [Technical Specifications] Action |
| Statement 3.6.3.D.1, which requires the unit to be taken to Mode 3 in 6 |
| hours when two containment isolation valves are inoperable for greater than |
| 1 hour. Valves 1SC-953 and 1SC-966B, pressurizer liquid space sampling |
| containment isolation valves, were declared inoperable when leakage was |
| evident past the shut valves. At 1748 hours, the pressurizer liquid space |
| penetration flow path was verified as being isolated by shutting manual |
| valve 1SC-952. The shutdown was terminated at 1751[CST] hours. |
| |
| "Earlier in the afternoon, it had been reported to the Control Room that the |
| reactor coolant primary sampling containment isolation valves (1SC-955 and |
| 1SC-966C) were leaking through. The penetration flow path for these valves |
| was isolated via shutting valve 1SC-954B. Further investigation revealed |
| that leakage was still present. The leakage was isolated by shutting |
| 1SC-952. |
| |
| "The 1D Pressurizer Heater Bank tripped during attempt to manually energize |
| pressurizer heaters. Minimum required pressurizer heater capacity is |
| maintained. Investigation is in progress." |
| |
| The licensee has notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 39625 |
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| FACILITY: COLUMBIA GENERATING STATIREGION: 4 |NOTIFICATION DATE: 02/27/2003|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 23:37[EST]|
| RXTYPE: [2] GE-5 |EVENT DATE: 02/27/2003|
+------------------------------------------------+EVENT TIME: 19:45[PST]|
| NRC NOTIFIED BY: CRAIG SLY |LAST UPDATE DATE: 02/27/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID GRAVES R4 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 100 Power Operation |80 Power Operation |
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EVENT TEXT
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| UNIT COMMENCED TECH SPEC REQUIRED SHUTDOWN DUE TO INOPERABLE EDG |
| |
| "This ENS notification is made to report initiation of a plant shutdown |
| required by the Columbia Generating Station Technical Specifications (TS's) |
| pursuant to 10CFR 50.72(b)(2)(i). This plant shutdown was initiated due to |
| the inability to restore the Division I Emergency Diesel Generator (DG-1) to |
| operable status prior to exceeding the expiration of the Completion Time of |
| TS LCO 3.8.1, Condition B.4. Columbia Generating Station was granted |
| enforcement discretion (NOED 03-4-001) from compliance with the completion |
| time requirements of TS 3.8.1, Condition B.4, for an eleven-day period |
| beginning on February 16, 2003 and ending February 27, 2003 at 9 p.m. (PST). |
| The enforcement discretion was granted to allow the replacement of a |
| degraded DG-1 generator bearing. Both generator bearings were replaced. |
| However, during post maintenance tests to validate operability of DG-1, |
| vibration levels for the new bearings showed evidence of an increasing |
| trend. Based on this, DG-1 is currently considered inoperable. Even |
| though the current vibration levels are very low, the plant has decided |
| further testing and diagnosis is necessary to support a decision on DG-1 |
| operability. Although the Completion Time of TS 3.8.1, Required Action B.4 |
| expires at 9 p.m., plant shutdown commenced at approximately 7:45 p.m. |
| (PST), on February 27, 2003." |
| |
| The licensee informed the NRC resident inspector. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021