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Event Notification Report for April 19, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/18/2001 - 04/19/2001

                              ** EVENT NUMBERS **

37761  37900  37905  37925  37926  37927  37928  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37761       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 02/19/2001|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 03:00[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        02/18/2001|
+------------------------------------------------+EVENT TIME:        22:45[EST]|
| NRC NOTIFIED BY:  VICTOR WALZ                  |LAST UPDATE DATE:  04/18/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLIFFORD ANDERSON    R1      |
|10 CFR SECTION:                                 |JOHN ZWOLINSKI       NRR     |
|*IND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION SYSTEM (HPCI) DECLARED INOPERABLE            |
|                                                                              |
| "During normal monitoring of the standby lineup of the High Pressure Coolant |
| Injection System (HPCI), the building rounds operator noticed that the HPCI  |
| discharge flow switch (23FS-78) was indicating 140 gpm with zero actual      |
| flow.  This flow switch controls the operation of the HPCI pump minimum flow |
| valve during HPCI operations.  Upon further investigation by the operating   |
| crew, it was also determined that the HPCI pump discharge flow transmitter   |
| was exhibiting sporadic flow spikes of 50 to 100 gpm with zero system flow.  |
| This flow signal is used to control HPCI turbine speed and flowrate.  Based  |
| on these findings, the HPCI system was declared inoperable per Technical     |
| Specification 3.5.c and a 7 day Limiting Condition for Operation was         |
| entered."                                                                    |
|                                                                              |
| The licensee called in an engineering team to address this problem.  The     |
| licensee will inform the NRC resident inspector.                             |
|                                                                              |
| * * * RETRACTION 1529 4/18/01 FROM PAGE TAKEN BY STRANSKY * * *              |
|                                                                              |
| "On 2/19/01 at 0300 EST, the James A. Fitzpatrick nuclear power plant        |
| notified the NRC that the High Pressure Coolant injection (HPCI) System had  |
| been declared inoperable due to indicated flow on a local discharge flow     |
| switch indication and sporadic flow spikes on the pump discharge flow        |
| transmitter while the system was in the standby lineup. The report was made  |
| pursuant to 10CFR50.72(b)(3)(v)(D) under Event Notification number 37761.    |
|                                                                              |
| "Based upon further review, it has been determined that, despite the         |
| problems noted, HPCI would have performed its safety function. The local     |
| HPCI discharge flow switch indication has no safety-related function. The    |
| associated safety-related switches operated within the prescribed setpoint   |
| tolerances. The hydraulic and mechanical portions of the system cannot       |
| respond to change as quickly as the electronic components, and therefore     |
| were not affected by the higher frequency sporadic spiking on the pump       |
| discharge flow transmitter. Maintenance was performed to address the         |
| associated degraded conditions.                                              |
|                                                                              |
| "Based upon the ability of the HPCI System to perform its safety function,   |
| the above notification is being retracted."                                  |
|                                                                              |
| The NRC resident inspector will be informed of this retraction. Notified     |
| R1DO (Ruland).                                                               |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37900       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 04/08/2001|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 22:15[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        04/08/2001|
+------------------------------------------------+EVENT TIME:        16:15[EDT]|
| NRC NOTIFIED BY:  RICHARD LANGE                |LAST UPDATE DATE:  04/18/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JACK MCFADDEN        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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE                         |
|                                                                              |
| "Both Division 1 and Division 2 standby diesel generators were declared      |
| inoperable. This report is being made per 10CFR50.72(b)(3)(v)(A), in that    |
| both standby diesels were in a condition such that they may not have been    |
| able to fulfill their intended safety function.                              |
|                                                                              |
| "The division 1 diesel generator was declared inoperable because both diesel |
| generator room exhaust fans were found rotating backwards.  The division 2   |
| diesel generator was declared inoperable due to one exhaust fan rotating     |
| backwards and the outside air temperature exceeding 72F. The cause of the   |
| fan blades' reverse rotation is under evaluation.  Reverse fan blade         |
| rotation may cause longer in-rush starting currents which could cause the    |
| fan motors to trip.                                                          |
|                                                                              |
| "With two diesel generators inoperable, the plant entered Technical          |
| Specification 3.8.1, a 2-hour shutdown Action Statement.                     |
|                                                                              |
| "Division 1 and 2 diesel room exhaust fans stopped rotating, and the outside |
| air temperature lowered to less than 72F The Technical Specification Action |
| Statements were exited. Periodic monitoring of the fans has been established |
| to address reoccurrence of the condition."                                   |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
|                                                                              |
| * * * RETRACTED AT 1400 EDT ON 4/18/01 BY THOMAS RESTUCCIO TO FANGIE JONES * |
| * *                                                                          |
|                                                                              |
| The licensee is retracting the event notification based on the following:    |
|                                                                              |
| "Event notification 37900 was written due to the inoperability of Division I |
| and II emergency diesel generators. The diesel generators were declared      |
| inoperable due to the diesel generator room exhaust fans spinning backwards. |
| The issue was that under reverse rotation, starting currents may exceed trip |
| values rendering the exhaust fans inoperable and, as a result, causing the   |
| diesel generators to be declared inoperable.                                 |
|                                                                              |
| "At the time of discovery it was identified that the diesel generator        |
| exhaust fans for Division I and II were observed to be rotating backwards at |
| approximately 10-15 rpms. An engineering analysis performed by the licensee  |
| has determined that the tans can be spinning backwards up to 235 rpm and     |
| will start and operate normally if needed. There will be no adverse affect   |
| on the fans operability to perform their design safety function."            |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R1DO (William Ruland) |
| was notified.                                                                |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37905       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ROBINSON                 REGION:  2  |NOTIFICATION DATE: 04/10/2001|
|    UNIT:  [2] [] []                 STATE:  SC |NOTIFICATION TIME: 18:49[EDT]|
|   RXTYPE: [2] W-3-LP                           |EVENT DATE:        04/10/2001|
+------------------------------------------------+EVENT TIME:        13:30[EDT]|
| NRC NOTIFIED BY:  HAROLD CHERNOFF              |LAST UPDATE DATE:  04/18/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE ERNSTES         R2      |
|10 CFR SECTION:                                 |                             |
|*DEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAKAGE POSSIBLY VIA A |
| CONTROL ROD DRIVE MECHANISM ASSEMBLY SEAL WELD                               |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On 4/10/01, during the removal of mirror insulation from the reactor vessel |
| head while shut down, deposits of residual boric acid were found on the      |
| periphery of the Reactor Pressure Vessel Head outside of the Control Rod     |
| Drive Mechanism (CRDM) Shroud.  Subsequent investigation, by visual          |
| inspection of the area within the shroud, revealed additional amounts of     |
| boric acid.  The source of the leak, based on initial observation, appears   |
| to be a CRDM assembly seal-weld leak about 18 inches above the vessel head   |
| insulation.  A leak from this location would constitute Reactor Coolant      |
| System Pressure Boundary leakage.  Initial inspection of the reactor vessel  |
| head areas, in the vicinity of the boric acid deposits outside of the        |
| shroud, revealed no damage to the reactor vessel head."                      |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE ON 04/18/01 @ 1123 BY GARROU TO GOULD * * *   RETRACTION        |
|                                                                              |
| On 4/10/01, during the removal of mirror insulation from the reactor vessel  |
| head while shut down.                                                        |
| deposits of residual boric acid crystals were found on the periphery of the  |
| Reactor Pressure Vessel                                                      |
| Head outside of the Control Rod Drive Mechanism (CRDM) shroud.   Subsequent  |
| inspection at CRDM canopy seal welds and the reactor vessel head in the      |
| vicinity of the boric acid crystal deposits was conducted with the head off  |
| the reactor vessel and the shroud and some mirror insulation removed.  The   |
| identified source of the observed boric acid crystals was two very small     |
| locations on the canopy seal weld of CRDM No. 68 at location B10.            |
|                                                                              |
| Leakage through the canopy seal weld is not pressure boundary leakage as     |
| described in the Technical Specifications and Bases.   The structural        |
| integrity of the CRDM housing is maintained by the threaded connection.      |
| The canopy seal weld does not maintain the structural integrity of the       |
| reactor coolant system. Therefore, the original notification made pursuant   |
| to 10CFR  50.72(b)(3)(ii)(A) is retracted.                                   |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| Reg 2 RDO(Landis) was notified.                                              |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37925       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 04/17/2001|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 17:40[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/17/2001|
+------------------------------------------------+EVENT TIME:        15:42[EDT]|
| NRC NOTIFIED BY:  SUE SIMPSON                  |LAST UPDATE DATE:  04/18/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM RULAND       R1      |
|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                                   
+------------------------------------------------------------------------------+
| VALID CONTAINMENT VENTILATION ISOLATION                                      |
|                                                                              |
| "While in Mode Undefined (core offloaded), Salem Unit 1 received a           |
| Containment Ventilation Isolation signal due to elevated count rate on       |
| 1R11A, the Containment Particulate Radiation Monitor. The 1R11A setpoint is  |
| set two times background in accordance with Tech Spec 3.3.3.1 for Mode 6.    |
| Background count rate prior to the CVI was 2100 cpm (counts per minute). The |
| alarm setpoint was 2980 cpm.                                                 |
|                                                                              |
| "The observed count rate when the actuation occurred was 3300 cpm.           |
| Maintenance activities in progress included the breech of 14SJ43, Cold Leg   |
| Injection Check Valve. Elevated airborne activity was expected due to this   |
| evolution and had been discussed by Control Room personnel. When 1R11A       |
| exceeded its setpoint, all containment ventilation isolation valves closed   |
| as designed. This actuation has not impacted the Unit 1 outage.              |
|                                                                              |
| "Plant status before and after event:                                        |
| Reactor Coolant System drained to mid-loop                                   |
| RCS at approximately 90F                                                    |
| Core completely offloaded                                                    |
| Mode Undefined"                                                              |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
|                                                                              |
| * * * Retraction 1213 4/18/2001 from Sue Simpson taken by Bob Stransky * *   |
| *                                                                            |
|                                                                              |
| "This notification is a retraction of the 8-hour report made IAW             |
| 10CFR50.72(b)(3)(iv)(A) on April 17, 2001 (event time 1542, reported at      |
| 1740).                                                                       |
|                                                                              |
| "This event notification is being retracted because subsequent investigation |
| determined that the containment ventilation isolation does not meet the      |
| definition of reportable system actuations listed in                         |
| 10CFR50.72(b)(3)(iv)(B)."                                                    |
|                                                                              |
| The NRC resident inspector will be informed by the licensee. Notified R1DO   |
| (Ruland).                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37926       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 04/18/2001|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 12:38[EDT]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        04/18/2001|
+------------------------------------------------+EVENT TIME:        11:50[EDT]|
| NRC NOTIFIED BY:  DAVID MORRIS                 |LAST UPDATE DATE:  04/18/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KERRY LANDIS         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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANNED OFFSITE NOTIFICATION REGARDING THE DISCOVERY OF A DEAD AMERICAN      |
| CROCODILE                                                                    |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[At 1150 on 04/18/01, the licensee was] notified by Land Utilization of a   |
| deceased American Crocodile.  [It was] discovered at [the] far west end of   |
| the cooling canals.  [The] State of Florida will be notified by Land         |
| Utilization later today."                                                    |
|                                                                              |
| The licensee notified the NRC resident inspector and plans to notify the     |
| State.  It was reported that the State may inform other federal agencies.    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37927       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  HI DEPARTMENT OF HEALTH              |NOTIFICATION DATE: 04/18/2001|
|LICENSEE:  CONSTRUCTION ENGINEERING LABS        |NOTIFICATION TIME: 15:29[EDT]|
|    CITY:  KAU                      REGION:  4  |EVENT DATE:        04/17/2001|
|  COUNTY:                            STATE:  HI |EVENT TIME:        15:30[HST]|
|LICENSE#:  53-23293-01           AGREEMENT:  N  |LAST UPDATE DATE:  04/18/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES MARSCHALL    R4      |
|                                                |DONALD COOL          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  J. NAKASONE                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NRC LICENSED SOURCE INVOLVED IN AUTOMOBILE ACCIDENT                          |
|                                                                              |
| The caller reported that an NRC licensed moisture/density gauge was involved |
| in an automobile accident. The gauge was in its case, which was undamaged.   |
| Radiation readings taken at the scene were less than 1 mR/hr. The state      |
| contacted the NRC licensee, and has already reported the event to NRC Region |
| IV.                                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37928       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 04/18/2001|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 17:45[EDT]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        04/18/2001|
+------------------------------------------------+EVENT TIME:        14:05[EDT]|
| NRC NOTIFIED BY:  LARRY TAYLOR                 |LAST UPDATE DATE:  04/18/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KERRY LANDIS         R2      |
|10 CFR SECTION:                                 |                             |
|*UNA 50.72(b)(3)(ii)(B)  UNANALYZED COND OP     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SAFE SHUTDOWN TRAIN ELECTRICAL SEPARATION NOT ADEQUATE                       |
|                                                                              |
| "HNP is in mode one, 100% power and stable. HNP personnel have determined    |
| during an engineering review that fuses intended to maintain safe shutdown   |
| train separation in the event of a fire in the 'A' Switchgear room are not   |
| capable of performing their intended function due to a design error. A fire  |
| in one fire area could result in the inability to isolate a Pressurizer      |
| Power Operated Relief Valve (PORV) and associated block valve. These fuses   |
| were intended to protect against this condition by isolating the PORV Block  |
| Valve circuit on an electrical short due to a fire. These fuses provide      |
| power for indication on the plant computer only.                             |
|                                                                              |
| "The fuses creating this condition have been removed restoring proper train  |
| separation."                                                                 |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+