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Event Notification Report for April 4, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/03/2001 - 04/04/2001

                              ** EVENT NUMBERS **

37634  37880  37883  37884  37885  37886  37887  37888  37889  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37634       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 12/27/2000|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 12:47[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        12/27/2000|
+------------------------------------------------+EVENT TIME:        10:31[EST]|
| NRC NOTIFIED BY:  RANDY HAISLET                |LAST UPDATE DATE:  04/03/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE DOERFLEIN   R1      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|NLTR                     LICENSEE 24 HR REPORT O|                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) DECLARED INOPERABLE             |
|                                                                              |
| The licensee was performing the procedure to reset the RCIC isolation, after |
| a surveillance was completed, when the closed inboard steam isolation valve  |
| (MO-1301-16) went to dual indication while opening the outboard steam        |
| isolation valve (MO-1301-17).  Both steam isolation valves to the RCIC       |
| turbine were closed and the RCIC system was declared inoperable.  The        |
| licensee is investigating the problem.                                       |
|                                                                              |
| Active limiting conditions for operation were entered for the RCIC system    |
| and the primary containment isolation function of the RCIC inboard steam     |
| isolation valve (MO-1301-16).                                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * RETRACTED AT 1414 EDT ON 4/3/01 BY ERIC OLSON TO FANGIE JONES * * *    |
|                                                                              |
| The licensee is retracting this event notification.  The following was       |
| submitted as the basis for the retraction.                                   |
|                                                                              |
| "On December 27, 2000, the RCIC system was taken out of service to perform   |
| routine surveillance in accordance with PNPS procedures 8.M.2-2.6.1 and      |
| 8.M.2-2.6.4. After resetting the RCIC isolation after performance of the     |
| High Steam Flow surveillance, operations personnel opened valve, MO-1301-17. |
| Approximately 5 seconds into the opening stroke, MO-1301-16, the inboard     |
| isolation valve, gave dual indication. During the initial opening of the     |
| MO-1301-17 valve, the RCIC turbine inlet steam line began to pressurize due  |
| to trapped pressure between the MO-1301-16 and MO-1301-17 valves and         |
| increased to approximately 437 psig when it began to decrease at about one   |
| pound per two seconds. The Control Room operator then gave MO-1301-16 valve  |
| a closed signal after the valve indicated dual indication for 16 seconds and |
| the valve then indicated full closed. The steam line continued to            |
| depressurize at the same rate until operations closed the MO-1301-17 valve.  |
| This indicated that although MO-1301-16 showed dual Indication, it was       |
| closed and the seating surfaces were tight and the containment isolation     |
| function was operable.                                                       |
|                                                                              |
| "The test that was being performed was testing the primary containment       |
| isolation system (PCIS) and this surveillance was satisfactory with both     |
| inboard and outboard isolation valves closing upon initiation. Additionally, |
| MO-1301-16 was stroke timed in accordance with PNPS procedure 8.5.5.4 and    |
| the times were within the expected limits.                                   |
|                                                                              |
| "After the initial indication of leakage, the Control Room management        |
| conservatively declared MO-1301-16 and the RCIC system inoperable until      |
| further investigation could be performed. Troubleshooting was conducted in   |
| accordance with PNPS procedure 3.M.1-34. The conclusion was that while dual  |
| indication had occurred, the valve had been closed and primary containment   |
| isolation was operable.                                                      |
|                                                                              |
| "For (a)(2)(i) (B): not reportable. The initial indication of leakage        |
| through containment Isolation valve MO-1301-16 was evaluated. The source of  |
| the pressure was steam trapped between the isolation valves during the       |
| previous testing. The valve was subsequently determined to have been closed  |
| and containment isolation was maintained.                                    |
|                                                                              |
| "For (a)(2)(v): not reportable. There was no component or system failure.    |
| The containment isolation function was maintained.                           |
|                                                                              |
| "For (a)(2)(vii): not reportable. It was determined that there was no        |
| component or system failure. The containment isolation function was          |
| maintained.                                                                  |
|                                                                              |
| "Please note that RCIC was 'made' inoperable by closing the referenced       |
| motor-operated valves (MO-1301-16 and MO-1301-17) to perform their primary   |
| containment isolation function in accordance with Technical Specification    |
| 3/4.7.A.2. After the operability determination, the valves were opened and   |
| RCIC was again operable per TS 3/4.5.D."                                     |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R1DO (Jack McFadden)  |
| was informed.                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37880       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 04/02/2001|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 06:53[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/02/2001|
+------------------------------------------------+EVENT TIME:        04:02[CST]|
| NRC NOTIFIED BY:  BEAUDIN                      |LAST UPDATE DATE:  04/04/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVE LOVELESS        R4      |
|10 CFR SECTION:                                 |                             |
|*DEG 50.72(b)(3)(ii)(A)  DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| GREATER THAN 1 PERCENT OF STEAM GENERATOR # 3 TUBES FOUND TO  BE POTENTIALLY |
| DEGRADED.                                                                    |
|                                                                              |
| At approximately 0402 CT on 04/02/01, Comanche Peak discovered that more     |
| than 1% (52 out of 4772 tubes) of the inspected tubes in Steam Generator # 3 |
| are potentially degraded.  The degraded tubes are being evaluated to be      |
| removed from service.  This event meets the criteria of C-3 as described in  |
| their Technical Specification section 5.5.9.  Additional data is being       |
| collected and will be analyzed to assist in determining the cause of the     |
| event.  An LER will be issued to further document this issue.  The other     |
| three Steam Generator tubes are being inspected.                             |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
|                                                                              |
| * * * UPDATE ON 04/03/01 AT 0653 ET BY RAUL MARTINEZ TAKEN BY MACKINNON * *  |
| *                                                                            |
|                                                                              |
| GREATER THAN 1 PERCENT OF STEAM GENERATOR # 4 TUBES FOUND TO BE POTENTIALLY  |
| DEFECTIVE.                                                                   |
|                                                                              |
| At approximately 0500 CT on 04/03/01 Comanche Peak discovered that more than |
| 1% (49 out of 4777 tubes) of the inspected tubes in Steam Generator # 4 are  |
| potentially defective.  The defective tubes are being evaluated to be        |
| removed from service.                                                        |
|                                                                              |
| This event meets the criteria of C-3 as described in the their Technical     |
| Specification section 5.5.9.  Additional data is being collected and will be |
| analyzed to assist in determining the cause of the event.                    |
|                                                                              |
| The licensee is presently inspecting Steam Generators 1 and 2.  R4DO (Linda  |
| Smith) notified.                                                             |
|                                                                              |
| The NRC Resident Inspector will be notified of this update by the licensee.  |
|                                                                              |
| ***** UPDATE AT 0015 EDT ON 04/04/01 FROM RAUL MARTINEZ TO LEIGH TROCINE     |
| *****                                                                        |
|                                                                              |
| GREATER THAN 1% OF THE INSPECTED STEAM GENERATOR #2 TUBES WERE FOUND TO BE   |
| POTENTIALLY DEFECTIVE.                                                       |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At approximately 2237 [CDT] on [04/03/01,] Comanche Peak Unit 1 discovered  |
| that more than 1% of the inspected tubes in steam generator #2 [were]        |
| potentially defective.  The defective tubes are being evaluated to be        |
| removed from service."                                                       |
|                                                                              |
| "This event meets the criteria of C-3 as described in [...] Technical        |
| Specification section 5.5.9 and is being reported pursuant to the            |
| requirements of 10 CFR 50.72(b)(3)(ii)(A).  Additional data is being         |
| collected and will be analyzed to assist in determining the cause of the     |
| event."                                                                      |
|                                                                              |
| "[The total number] of inservice tubes in [steam generator] #2 = 4,476       |
| tubes[, and the total number] of tubes discovered defective at this time =   |
| 52 tubes."                                                                   |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  The NRC operations |
| officer notified the R4DO (Linda Smith).                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37883       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MALLINCKRODT, INC.                   |NOTIFICATION DATE: 04/03/2001|
|LICENSEE:  MALLINCKRODT,INC.                    |NOTIFICATION TIME: 11:59[EDT]|
|    CITY:  MINNEAPOLIS ST. PAUL     REGION:  3  |EVENT DATE:        04/03/2001|
|  COUNTY:                            STATE:  MN |EVENT TIME:             [CDT]|
|LICENSE#:  24-17450-02MD         AGREEMENT:  N  |LAST UPDATE DATE:  04/03/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MICHAEL JORDAN       R3      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  WILLIAM CRAWFORD             |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PHARMACY RECEIVED GENERATOR WITH SLIGHTLY HIGH SURFACE READING               |
|                                                                              |
| The Mallinckrodt Pharmacy received a generator with a surface reading of     |
| slightly greater than the 200 millirem per hour from the Mallinckrodt        |
| facility in St. Louis, Missouri.  There was no surface contamination, the    |
| swipe test was negative.  The package had a transport index of 6.0 with a    |
| yellow 3 label package with transport index of 1.5.  The manufacturer has    |
| been notified and is investigating the event.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37884       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 04/03/2001|
|LICENSEE:  GEO SOLUTIONS                        |NOTIFICATION TIME: 14:10[EDT]|
|    CITY:  SAN LUIS OBISPO          REGION:  4  |EVENT DATE:        04/03/2001|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PDT]|
|LICENSE#:  6286-40               AGREEMENT:  Y  |LAST UPDATE DATE:  04/03/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA SMITH          R4      |
|                                                |CHARLES COX          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  RECA OMAR                    |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MOISTURE DENSITY GAUGE RUN OVER AND DAMAGED                                  |
|                                                                              |
| Geo Solutions reported to the State of California that a Humbolt moisture    |
| density gauge was run over at a work site in Atascadero, CA.  The case is    |
| cracked, but the insides appear intact.  The licensee is contacting the      |
| vendor for proper handling.  There is no further information at this time.   |
|                                                                              |
| * * * UPDATED AT 1732 EDT ON 4/3/01 BY RECA OMAR TO FANGIE JONES * * *       |
|                                                                              |
| Geo Solutions Radiation Safety Officer made a further report about the       |
| gauge.  The source is intact, the electronics are still working, and a       |
| survey indicated no leakage.  The gauge has been placed in storage until the |
| vendor takes possession and performs a leak test.  A construction bulldozer  |
| ran over the gauge.                                                          |
|                                                                              |
| The R4DO (Linda Smith) and the NMSS EO (Patricia Holahan) were notified.     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37885       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 04/03/2001|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 15:03[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        04/03/2001|
+------------------------------------------------+EVENT TIME:        12:00[CDT]|
| NRC NOTIFIED BY:  ERNEST MATES                 |LAST UPDATE DATE:  04/03/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LINDA SMITH          R4      |
|10 CFR SECTION:                                 |                             |
|*PRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NOTIFICATION OF LOCAL GOVERNMENT AGENCY DUE TO SPURIOUS SIREN ACTUATION      |
|                                                                              |
| The licensee notified Claiborne County Civil Defense that a single offsite   |
| emergency siren sounded spuriously for about 25 minutes today starting about |
| 1200 CDT.                                                                    |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37886       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 04/03/2001|
|    UNIT:  [1] [2] []                STATE:  FL |NOTIFICATION TIME: 16:12[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        04/03/2001|
+------------------------------------------------+EVENT TIME:        16:09[EDT]|
| NRC NOTIFIED BY:  C. D.  MARPLE                |LAST UPDATE DATE:  04/03/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KEN BARR             R2      |
|10 CFR SECTION:                                 |                             |
|*PRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STATE AGENCY NOTIFIED OF INJURED LOGGERHEAD TURTLE FOUND IN THE INTAKE       |
| CANAL                                                                        |
|                                                                              |
| The licensee notified the Florida Fish and Wildlife Conservation Commission  |
| regarding an injured loggerhead turtle found in the plant's intake canal.    |
| The turtle will be sent out for rehabilitation.                              |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37887       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 04/04/2001|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 02:19[EDT]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        04/03/2001|
+------------------------------------------------+EVENT TIME:        23:58[CDT]|
| NRC NOTIFIED BY:  RON WIGGINS                  |LAST UPDATE DATE:  04/04/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHAEL PARKER       R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       27       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM FROM 27% POWER DUE TO A RECIRULATION PUMP TRIP FOR      |
| UNKNOWN REASONS WHILE THE UNIT WAS IN SINGLE LOOP OPERATION                  |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[The] unit was operating [in] single loop (2A [recirculation] pump          |
| operating) when the 2A [recirculation] pump tripped.  The [nuclear station   |
| operator] manually scrammed the unit as required by procedure.  During the   |
| event, Group II and III isolations were received.  All equipment operated as |
| expected.  [The] unit is [currently] stable in Mode 3.  Restart is being     |
| evaluated."                                                                  |
|                                                                              |
| The licensee stated that reactor vessel water level decreased to +5 inches   |
| and that the Group II and III isolation setpoint was +8 inches.  The Group   |
| II and III isolations have been reset, and ventilation has been restored.    |
|                                                                              |
| The normal reactor feedwater system is currently being utilized to supply    |
| water to the reactor vessel, and containment parameters are normal.  The     |
| steam dumps to the condenser were available but not needed.                  |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37888       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 04/04/2001|
|    UNIT:  [] [2] []                 STATE:  AL |NOTIFICATION TIME: 07:22[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        04/03/2001|
+------------------------------------------------+EVENT TIME:        23:51[CDT]|
| NRC NOTIFIED BY:  DAVID TIDWELL                |LAST UPDATE DATE:  04/04/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KEN BARR             R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR SCRAM ON WEST SCRAM DISCHARGE VOLUME HIGH WATER LEVEL DUE TO         |
| APPARENT LEAKAGE THROUGH THE SCRAM VALVES                                    |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During a refueling outage while picking up a hold order on the control rod  |
| drive system, water level in the scram discharge volume instrument volume    |
| started to rise from apparent leakage through the scram valves.  At 2351     |
| [CDT,] a reactor scram was received on the west scram [discharge volume]     |
| high water level.  All expected alarms and actuations were received.  All    |
| control rods were initially 'full in,' and no rod movement occurred."        |
|                                                                              |
| The licensee stated that there was nothing unusual or misunderstood and that |
| all systems functioned as required.  The licensee also stated that at the    |
| time of the event, work was being performed on the scram discharge volume    |
| drain valves which prevented the scram discharge volume from draining.       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37889       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 04/04/2001|
|    UNIT:  [1] [] []                 STATE:  FL |NOTIFICATION TIME: 10:50[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        04/04/2001|
+------------------------------------------------+EVENT TIME:        10:12[EDT]|
| NRC NOTIFIED BY:  DAVE WILLIAMS                |LAST UPDATE DATE:  04/04/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |KEN BARR             R2      |
|10 CFR SECTION:                                 |TAD MARSH            NRR     |
|AAEC 50.72(a)(1)(i)      EMERGENCY DECLARED OBSO|RICHARD WESSMAN      IRO     |
|                                                |GARY BELCHER         FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| REACTOR COOLANT SYSTEM LEAKAGE >10 GPM AS OBSERVED FROM CONTROL ROOM         |
| INDICATIONS                                                                  |
|                                                                              |
| "EMERGENCY PLAN ENTRY DUE TO CONTROL ROOM INDICATION OF REACTOR COOLANT      |
| SYSTEM LEAKAGE GREATER THAN 10 GPM.  IT APPEARS THAT SHUTDOWN COOLING RELIEF |
| VALVE V-3483 LIFTED WHILE ATTEMPTING TO PLACE '1A' TRAIN OF SHUTDOWN COOLING |
| IN SERVICE.  WHEN V-3481, HOT LEG SUCTION VALVE, WAS OPENED, APPROXIMATELY   |
| 300 GALLONS OF REACTOR COOLANT WAS DIVERTED TO A HOLDUP TANK OVER A PERIOD   |
| OF 2 MINUTES.  THE LEAK, ESTIMATED AT 150 GPM, WAS ISOLATED BY CLOSING HOT   |
| LEG SUCTION VALVE V-3480.  AN UNUSUAL EVENT WAS ENTERED AND TERMINATED       |
| IMMEDIATELY AT 1012 HOURS AS THE LEAK HAD BEEN TERMINATED AT THE TIME OF THE |
| NOTIFICATION.                                                                |
|                                                                              |
| "THIS EVENT IS SIMILAR TO EVENT #37882."                                     |
|                                                                              |
| RCS PRESSURE AND TEMPERATURE IS CURRENTLY 260 PSIG AND 250 DEGREES F,        |
| RESPECTIVELY.  THE RELIEF VALVE SETPOINT IS 330 PSIG.  FOLLOWING THE         |
| PREVIOUS EVENT, THE RELIEF VALVE V-3483 WAS REMOVED AND BENCH TESTED WITH NO |
| ABNORMALITIES RELATED TO THE SETPOINT PRESSURE FOUND.  PRESENTLY, THERE ARE  |
| TWO (2) RCPs RUNNING WITH A THIRD AVAILABLE AND THE "1B" SHUTDOWN COOLING    |
| TRAIN IN SERVICE.  THE LICENSEE PER A PROCEDURAL  REQUIREMENT INVOLVING LOW  |
| PRESSURE OPERATION OF THE RCPs (RCP SEAL PROTECTION) IS IN A 12 HOUR TIME    |
| PERIOD ENDING AT 1600 HOURS.  THE CURRENT PLANS ARE TO INCREASE RCS PRESSURE |
| TO GREATER THAN 350 PSIG.  BOTH STEAM GENERATORS ARE AVAILABLE TO REMOVE     |
| DECAY HEAT.  UNIT 1 HAS BEEN SHUTDOWN FOR APPROXIMATELY 50 HOURS.  AN EVENT  |
| RESPONSE TEAM HAS BEEN ASSEMBLED TO RECOMMEND APPROPRIATE CORRECTIVE ACTIONS |
| FOLLOWING COMPLETION OF AN INVESTIGATION.                                    |
|                                                                              |
| THE LICENSEE INFORMED STATE/LOCAL AGENCIES AND THE NRC RESIDENT INSPECTOR.   |
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