Event Notification Report for April 23, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/20/2001 - 04/23/2001
** EVENT NUMBERS **
37934 37935 37936 37937 37938 37939
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|Power Reactor |Event Number: 37934 |
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| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 04/20/2001|
| UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 10:19[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 03/10/2001|
+------------------------------------------------+EVENT TIME: 13:30[EDT]|
| NRC NOTIFIED BY: SAARE |LAST UPDATE DATE: 04/20/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM RULAND R1 |
|10 CFR SECTION: | |
|*INV 50.73(a)(1) INVALID SPECIF SYSTEM A| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| INVALID ACTUATION OF THE "B" EMERGENCY SERVICE WATER PUMP OCCURRED |
| |
| This 60-day optional report, as allowed by 10 CFR 50.73(a)(1), is being made |
| under the reporting requirement in 10CFR50.73(a)(2)(iv)(A) to describe an |
| invalid actuation of a specified system, specifically Emergency Service |
| Water (ESW). |
| |
| On March 10, 2001, during performance of a surveillance test on the |
| Emergency Diesel Generator Logic, an invalid actuation of the "B" ESW pump |
| occurred. The event was caused by a jumper inadvertently being left |
| installed when the surveillance test required the jumper to be momentarily |
| installed. The jumper simulated an initiation signal on 1 EDG. As the |
| test progressed, the "B" ESW pump received an initiation signal and |
| started. |
| |
| The "B" ESW pump started as expected for the given conditions and was |
| subsequently returned to standby per plant procedures. No deficiencies |
| were noted during operation of the "B" ESW pump. |
| |
| This event has been entered into the site-specific corrective action program |
| for resolution. |
| |
| The resident has been informed. |
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|General Information or Other |Event Number: 37935 |
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| REP ORG: OK DEQ RAD MANAGEMENT |NOTIFICATION DATE: 04/20/2001|
|LICENSEE: GEO SYSTEMS ENGINEERING, INC. |NOTIFICATION TIME: 12:40[EDT]|
| CITY: TULSA REGION: 4 |EVENT DATE: 04/20/2001|
| COUNTY: STATE: OK |EVENT TIME: 06:20[CDT]|
|LICENSE#: 27597-02-OK AGREEMENT: Y |LAST UPDATE DATE: 04/20/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES MARSCHALL R4 |
| |JOSEPHINE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MAKE BRODERICK | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| AGREEMENT STATE REPORT - STOLEN HUMBOLDT NUCLEAR GAUGE |
| |
| The device was stolen from a truck after the chain had been cut, the travel |
| case was locked. The theft was reported to the Tulsa police department and |
| a reward will be offered by the licensee. The device was a Humboldt model |
| 5001B serial #3475 containing Cs-137 and Am-241. |
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|Power Reactor |Event Number: 37936 |
+------------------------------------------------------------------------------+
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| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 04/21/2001|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 02:31[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 04/20/2001|
+------------------------------------------------+EVENT TIME: 19:31[CDT]|
| NRC NOTIFIED BY: SCOTT MAGLIO |LAST UPDATE DATE: 04/21/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES MARSCHALL R4 |
|10 CFR SECTION: | |
|*ESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| UNANTICIPATED EMERGENCY DIESEL GENERATOR START DURING THE PERFORMANCE OF |
| TESTING |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "This is notification of valid system actuation in accordance with |
| 10CFR50.72(b)(3)(iv)(A)." |
| |
| "At 1931 [CDT] on 04/20/01, the 'B' emergency diesel generator (EDG) |
| automatically started during testing of the local emergency start |
| pushbutton. This was conducted as part of a pre-planned test for |
| restoration following maintenance. However, during the test, the system |
| actuated in a way that was not part of the planned test. Initial test of |
| the signal was unsuccessful, and the start signal was not reset prior to |
| restoring the EDG to the standby lineup. Subsequently, when the start |
| failure relay was locally reset, the EDG automatically started." |
| |
| "The unit was in no MODE at the time of the actuation." |
| |
| The licensee plans to notify the NRC resident inspector. |
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|Power Reactor |Event Number: 37937 |
+------------------------------------------------------------------------------+
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| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 04/21/2001|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 07:02[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 04/21/2001|
+------------------------------------------------+EVENT TIME: 03:20[CDT]|
| NRC NOTIFIED BY: JOHN LECHMAIER |LAST UPDATE DATE: 04/21/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RONALD GARDNER R3 |
|10 CFR SECTION: | |
|*IND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNIT 2 HPCI INOPERABLE DUE TO FAILED TURBINE EXHAUST LINE VACUUM BREAKER |
| CHECK VALVES |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 0320 [CDT] on April 21, 2001, Unit [2] HPCI was declared inoperable when |
| two check valves failed to meet acceptance criteria during the performance |
| of [procedure] QCOS 2300-18, HPCI STEAM EXHAUST VACUUM BREAKER LINE CHECK |
| VALVES IST FUNCTIONAL TEST. Two of the four HPCI turbine exhaust line |
| vacuum breaker check valves were found to have failed to close. The exhaust |
| line containing the failed check valves was isolated at the start of the |
| surveillance using motor-operated isolation valves contained in the exhaust |
| line. The failed check valves remain isolated." |
| |
| The licensee stated that Unit 2 is in a 14-day limiting condition for |
| operation as a result of this issue. |
| |
| The licensee notified the NRC resident inspector. |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37938 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 04/21/2001|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 10:19[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 04/21/2001|
+------------------------------------------------+EVENT TIME: 08:53[EDT]|
| NRC NOTIFIED BY: ERIC OLSON |LAST UPDATE DATE: 04/21/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM RULAND R1 |
|10 CFR SECTION: | |
|*INA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNANTICIPATED AUTOMATIC MAIN STEAM ISOLATION VALVE (MSIV) CLOSURE AND |
| REACTOR WATER CLEANUP [RWCU] SYSTEM ISOLATION DUE TO LEVEL RACK REFERENCE |
| LEG NOTCHING |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During cooldown of the reactor vessel with all rods fully inserted, the |
| [MSIVs] automatically closed in response to a reactor high level concurrent |
| with low reactor pressure (main steam line pressure <810 with reactor level |
| at |
| +55.4 inches). Reactor pressure was at 100 psig when the isolation |
| occurred. Approximately 1 hour later, another level perturbation occurred |
| resulting in automatic isolation of the [RWCU] system and the inboard MSIV |
| drain valve. The level perturbations are occurring in the 'A' train level |
| rack only. It appears to be caused by non-condensable gasses coming out of |
| solution in the 'A' level rack reference leg (notching). The 'A' train |
| water level indication system is considered to be inoperable, and the |
| applicable [limiting condition for operation] actions have been taken." |
| |
| The licensee stated that a planned reactor scram was performed prior to this |
| event in order to facilitate commencement of a scheduled refueling outage. |
| Apparently, the RWCU system isolation resulted from a spurious low level |
| signal to the actuation system when the reference leg was being back filled. |
| This was reported to be so quick that it was not seen on any control room |
| instruments. The RWCU system has been placed back in service and is being |
| used for level control. The MSIVs are still closed, but the isolation |
| signal has been reset. However, the notching phenomenon is still being |
| experienced. |
| |
| The licensee plans to change the decay heat removal path from the main steam |
| system and place the RCIC system in test mode. As the reference leg is back |
| filled and flushed out, the licensee plans to plan to go back to utilization |
| of the main steam system. |
| |
| The NRC resident inspector has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37939 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 04/21/2001|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 19:17[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 04/21/2001|
+------------------------------------------------+EVENT TIME: 14:54[CDT]|
| NRC NOTIFIED BY: JOHN CARLSON |LAST UPDATE DATE: 04/21/2001|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES MARSCHALL R4 |
|10 CFR SECTION: | |
|*RPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 58 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNEXPECTED AUTOMATIC REACTOR SCRAM DURING TURBINE CONTROL VALVE TESTING |
| |
| During plant start-up from forced outage 01-01, with the plant at 58% power, |
| an automatic reactor scram occurred. The scram occurred during the main |
| turbine control valve testing due to an apparent turbine pressure control |
| system malfunction. Automatic reactor scram occurred at the RPV High |
| Pressure Scram Setpoint. All other systems functioned as expected during |
| and after the transient. The unit is currently stable in Mode 3, Hot |
| Shutdown, with reactor pressure and level within normal bands. |
| Investigation in progress to determine cause of malfunction. Safety Relief |
| Valves opened and closed during the transient. All Emergency Core Cooling |
| Systems are fully operable and the electrical grid is stable. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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