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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|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 !!!!!!!
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|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 72�F. 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 72�F 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. |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|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. |
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!!!!!!!!! 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 90�F |
| 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. |
+------------------------------------------------------------------------------+
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