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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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37935       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37936       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37937       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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.       |
+------------------------------------------------------------------------------+