Event Notification Report for October 5, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/04/2000 - 10/05/2000
** EVENT NUMBERS **
37392 37393 37407 37408 37409 37410
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Fuel Cycle Facility |Event Number: 37392 |
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/29/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:46[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/29/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:22[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/04/2000|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |BRENT CLAYTON R3 |
| DOCKET: 0707001 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: UNDERWOOD | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| SAFETY SYSTEM ACTUATION |
| |
| At 1522 on 09/29/00, the PSS office was notified that a secondary condensate |
| alarm was received on the C-360 position 3 autoclave Water Inventory Control |
| System (WICS). The WICS system is required to be operable while heating in |
| mode 5 according to TSR 2.1.4.3. The autoclave was checked according to the |
| alarm response procedure, removed from service and the WICS system was |
| declared inoperable by the Plant Shift Superintendent. Troubleshooting was |
| initiated and is continuing in order to determine the reason for the alarm. |
| |
| The safety system actuation is reportable to the NRC as required by Safety |
| Analysis Report section 6.9, table 1 criterion J.2 Safety System actuation |
| due to a valid signal as a 24-hour event notification |
| |
| The NRC Senior Resident has bean notified of this event. |
| |
| ***** RETRACTION RECEIVED AT 2155 EDT ON 10/04/00 FROM KEVIN BEASLEY TO |
| LEIGH TROCINE ***** |
| |
| The following text is a portion of a facsimile received from Paducah |
| personnel: |
| |
| "THIS EVENT HAS BEEN RETRACTED. Investigation and troubleshooting by the |
| System Engineer revealed that the gain adjustment on one of the WICS |
| channels had drifted out of tolerance. Historical discussions with the |
| component manufacturer had concluded that the WICS alarm cards are |
| susceptible to drift, due to age and fluctuations in temperature. These |
| cards are exposed to ambient temperatures, but the cards are rated for the |
| range of temperatures at the autoclaves. Given this and other indications |
| that the WICS actuation signals were invalid, i.e., not the result of water |
| backing up in the drain, it has been concluded that the subject actuations |
| were caused by invalid signals (instrument drift) and thus, [do] not meet |
| the criteria for reporting." |
| |
| Paducah personnel notified the NRC resident inspector. The NRC operations |
| officer notified the R3DO (Madera) and NMSS EO (Hodges). |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 37393 |
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| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 09/30/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 05:14[EDT]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 09/30/2000|
+------------------------------------------------+EVENT TIME: 01:10[CDT]|
| NRC NOTIFIED BY: HILL |LAST UPDATE DATE: 10/04/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 85 Power Operation |85 Power Operation |
| | |
| | |
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EVENT TEXT
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| HPCI DECLARED INOPERABLE AND THE UNIT ENTERED A 14 DAY LCO ACTION |
| STATEMENT. |
| |
| At 0110 hours on September 30, 2000, the Unit One High Pressure Cooling |
| Injection (HPCI) system was declared inoperable following failure to |
| successfully complete QCOS 2300-26, HPCI CCST Suction Check Valve Closure |
| Test. QCOS 2300-26 is an Inservice Testing surveillance used to verify |
| closure of the HPCI pump Contaminated Condensate Storage Tank (CCST) suction |
| check valve. The valve could not be verified to be closed by the |
| surveillance and the system was declared inoperable, as required by the |
| procedure. The time of the LCO entry was at 0048 hours when the system was |
| made inoperable for performance of the surveillance. Unit One is currently |
| in a 14 day LCO per Technical Specification 3.5.A.3. The HPCI system is |
| currently in the normal standby line-up, available for injection if |
| required, pending troubleshooting. |
| |
| The NRC Resident Inspector was notified. |
| |
| ***** RETRACTION RECEIVED AT 1724 EDT ON 10/04/00 FROM DAVE BOWMAN TO LEIGH |
| TROCINE ***** |
| |
| The licensee is retracting this event notification. The following text is a |
| portion of a facsimile received from the licensee: |
| |
| "This is a retraction of the ENS call made on 09/30/00 concerning the |
| inoperabilty of the HPCI system following the failure of the HPCI |
| Contaminated Condensate Storage Tank (CCST) suction check valve to close |
| during a surveillance." |
| |
| "We have completed our evaluation and have determined that a redundant |
| isolation valve was operable and would have isolated the CCST suction to |
| HPCI and would not have prevented the HPCI alternate suction from the torus |
| to provide an adequate source of water for HPCI to meet its safety |
| function." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R3DO (Madera). |
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|Power Reactor |Event Number: 37407 |
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| FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 10/04/2000|
| UNIT: [] [] [3] STATE: IL |NOTIFICATION TIME: 01:23[EDT]|
| RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 10/03/2000|
+------------------------------------------------+EVENT TIME: 21:51[CDT]|
| NRC NOTIFIED BY: SALGADO |LAST UPDATE DATE: 10/04/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N Y 23 Power Operation |23 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE |
| |
| Failed to receive proper indication of turbine position circuitry indicating |
| lamp following HPCI system run at rated pressure. Investigation by station |
| personnel identified a failed oil pressure switch which provides indication |
| of stop valve closure to turbine reset circuit. |
| |
| Failure of the switch prevents automatic and remote reset of HPCI turbine |
| trips. This failure renders HPCI inoperable and would prevent it from |
| fulfilling its safety function. Technical Specification 3.5.a (14 days to |
| return to service or shutdown) entered. All other Emergency Core Cooling |
| Systems are fully operable. |
| |
| Efforts are proceeding to repair/replace the switch. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
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|Fuel Cycle Facility |Event Number: 37408 |
+------------------------------------------------------------------------------+
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| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/04/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 09:33[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/03/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:28[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/04/2000|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |JOHN MADERA R3 |
| DOCKET: 0707001 |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: M C PITTMAN | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| LOAD CELL CALIBRATION DATA FOR SOME FREEZER SUBLIMERS WERE FOUND TO BE NON |
| - CONSERVATIVE. |
| |
| At 1528 on 10/03/00, the Plant Shift Superintendent (PSS) was notified by |
| engineering that load cell calibration data for some freezer sublimers was |
| suspected to be in error. The load cells are part of the High High Weight |
| Trip System for the freezer sublimers which is required by Technical Safety |
| Requirement (TSR) to be operable. Data for many of the load cells |
| calibrated on site shows the identified load cells do not meet the |
| specifications credited in the existing setpoint calculations and the |
| calibration procedures. The problem appears to be consistent among the load |
| cells. The load cells data indicates less weight than what was actually |
| applied. It has been determined that this deficiency may affect the ability |
| of the freezer sublimers' ability to actuate the High High Weight Trip |
| System at the required Limited Control Setting (LCS). This deficiency would |
| not affect the ability of the freezer sublimers to actuate the High High |
| Weight Trip System below the Safety Limit (SL). There are 30 of the 10,000 |
| lb. Capacity and 4 of the 20,000 lb. capacity load cells that are affected. |
| Investigation revealed that none of the four 20,000 lb. Load cells have been |
| installed. The 20,000 lb. Load cells are being controlled to ensure they |
| are not installed. The affected in service freezer sublimers were declared |
| inoperable by the PSS. Engineering is reviewing work package data and the |
| freezer sublimers that do not contain suspected load cells are being |
| returned to service. Resolution of this issue is being pursued by |
| Operations, Maintenance, and Engineering. |
| |
| The equipment is required by TSR to be available and operable and should |
| have been operating. No redundant equipment is available and operable to |
| perform the required safety function. |
| |
| The NRC Resident Inspector ahs been notified of this event. |
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|Power Reactor |Event Number: 37409 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 10/04/2000|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 11:12[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 10/03/2000|
+------------------------------------------------+EVENT TIME: 20:55[CDT]|
| NRC NOTIFIED BY: OLMSTEAD |LAST UPDATE DATE: 10/04/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVE LOVELESS R4 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| NON - LICENSED OPERATOR INADVERTENTLY STARTED THE "A" EMERGENCY DIESEL |
| GENERATOR (EDG). |
| |
| At 2055 on October 3, 2000, the "A" EDG received an emergency start signal |
| in response to an inadvertent actuation of the EDG local emergency start |
| pushbutton. The local emergency start pushbutton was inadvertently actuated |
| by non-licensed Operations personnel while reviewing procedural guidance for |
| emergency starting the EDG from the local control panel. |
| |
| The EDG achieved rated voltage and speed following the start signal, but |
| was not required to connect to the Class 1E distribution system during the |
| event. The EDG was subsequently secured and restored to a standby status. |
| |
| Evaluations to determine the cause for why reporting requirement |
| 10CFR50.72(b)(2)(ii) was not initially identified will be addressed within |
| the station's corrective action program. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37410 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 10/04/2000|
| UNIT: [1] [2] [] STATE: WI |NOTIFICATION TIME: 19:50[EDT]|
| RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/04/2000|
+------------------------------------------------+EVENT TIME: 18:20[CDT]|
| NRC NOTIFIED BY: MIKE MEYER |LAST UPDATE DATE: 10/04/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| POTENTIAL OUTSIDE DESIGN BASIS ISSUE DUE TO LACK OF DOCUMENTATION TO SHOW |
| THAT ATMOSPHERIC STEAM DUMP VALVE CAPACITY WILL SUPPORT THE COOLDOWN |
| ASSUMPTIONS FOR A STEAM GENERATOR TUBE RUPTURE EVENT WHEN OFFSITE POWER IS |
| NOT AVAILABLE |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During a main steam and steam dump system validation, no documentation |
| could be found to show that the atmospheric steam dump (ADV) valve capacity |
| will support the 44-minute cooldown assumptions for a steam generator tube |
| rupture (SGTR) event as described in the FSAR when offsite power is not |
| available. FSAR Chapter 14 and plant procedures include assumptions and |
| procedure steps that require use of the [ADVs] to cool down the reactor |
| coolant system (RCS) within 44 minutes of a SGTR event to allow the RCS |
| pressure to equalize with the faulted steam generator pressure to terminate |
| primary to secondary break flow. The SGTR radiological dose assessment is |
| based upon this 44-minute time frame for ending flow to the ruptured steam |
| generator." |
| |
| "The current licensing basis calculation for the SGTR event calculates steam |
| releases from the intact and the faulted steam generators for the purpose of |
| determining offsite dose releases. However, this calculation does not |
| appear to support a demonstration of the capability of the ADV on the intact |
| steam generator to reduce the primary system temperature (with sufficient |
| subcooling margin) to allow depressurizing the RCS to equilibrium pressure |
| with the faulted steam generator. No calculation or other documentation has |
| been located that provides an evaluation of the amount of heat in the form |
| of steam to be removed by the intact steam generator's ADV to provide the |
| cooldown within the 44-minute time assumed in the accident analysis. An |
| operability determination is being performed per [Generic Letter] 91-18." |
| |
| The licensee stated that there was nothing unusual or not understood and |
| that all systems functioned as required. The licensee also stated that the |
| units were not in any limiting conditions for operation as a result of this |
| issue. |
| |
| The licensee notified the NRC resident inspector. |
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