Event Notification Report for December 2, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
12/01/1999 - 12/02/1999
** EVENT NUMBERS **
36332 36353 36476 36477 36478
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|General Information or Other |Event Number: 36332 |
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| REP ORG: ENERTECH |NOTIFICATION DATE: 10/22/1999|
|LICENSEE: ENERTECH |NOTIFICATION TIME: 15:37[EDT]|
| CITY: BREA REGION: 4 |EVENT DATE: 10/22/1999|
| COUNTY: STATE: CA |EVENT TIME: 10:00[PDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 12/01/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA SMITH R4 |
| |VERN HODGE (by fax) NRR |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JOHN DeKLEINE | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| - Potential 10CFR Part 21 Report - |
| |
| In late 1998 Enertech manufactured and shipped electro-hydraulic actuators |
| for installation on valves to be installed in an overseas plant. Prior to |
| shipment, the valve manufacturer observed pressure switch indication |
| problems during final testing of the valves on which the actuators were |
| installed. |
| |
| Collective investigation by Burns and Roe, Enertech, including its switch |
| supplier and the valve manufacturer determined the problem resulted from |
| changes in manufacturing methods implemented by the switch supplier. The |
| immediate problem was addressed, the pressure switches were modified using |
| the supplier's previous manufacturing methods, installed on the valves and |
| subsequently passed all final test requirements. |
| |
| * * * RETRACTION 1715 12/01/1999 FROM LEACHMAN (BY FAX) INPUT BY STRANSKY * |
| * * |
| |
| "On October 22, 1999 Enertech preliminarily notified the NRC of a potential |
| deficiency in our Commercial Dedication Program. In that correspondence we |
| stated that we had initiated an investigation to determine if previously |
| shipped items which were dedicated by Enertech comply with EPRI and |
| regulatory requirements. We further stated a final report would be issued |
| the end of November 1999. We have performed a programmatic review in an |
| effort to assure dedication activities performed by Enertech are in |
| accordance with known accepted Industry guidelines and requirements. We have |
| evaluated our processes for maintenance of equipment qualification in |
| accordance with established Industry guidelines and found our system is |
| fully compliant. Enertech has concluded a reportable condition does not |
| exist." |
| |
| Notified NRR (Hodges) via fax. |
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|Power Reactor |Event Number: 36353 |
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| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 10/26/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 22:51[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 10/26/1999|
+------------------------------------------------+EVENT TIME: 19:20[CDT]|
| NRC NOTIFIED BY: MARSHALL FUNKHOUSER |LAST UPDATE DATE: 12/01/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN 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 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| HIGH PRESSURE CORE SPRAY (HPCS) DECLARED INOPERABLE DUE TO ITS MINIMUM FLOW |
| VALVE FAILING TO FULLY OPEN. |
| |
| Clinton Power Station is presently performing a planned Division-3 (HPCS |
| diesel) outage. The plant has been in a limited condition for operation |
| allowed by technical specifications for this outage since 0230 CDT on |
| 10/26/99. At 1920 CDT on 10/26/99 during performance of a high pressure |
| spray system surveillance the HPCS minimum flow valve (1E22-F012) failed to |
| operate properly. During an open stroke of the minimum flow valve, power |
| was lost due to a breaker trip, and the valve failed to fully open. This |
| valve provides a minimum amount of flow through the system to ensure that |
| the pump does not overheat. The plant's technical specification provides |
| allowances for this condition, but 10CFR50.72(b)(2)(iii)(D) requires that a |
| component failure that could have prevented an independent safety system |
| from performing its function be reported. This system may have failed to |
| perform its safety function due to the failure of this valve; thus, this |
| report is being made. The licensee entered Technical Specification 3.5.1 |
| (14-day limiting condition of operation). The reactor core isolation |
| cooling system and all emergency core cooling systems are fully operable if |
| needed. The electrical grid is stable, and the Division 1 and 2 emergency |
| diesel generators are fully operable. |
| |
| The NRC resident inspector was notified of this event by the licensee. |
| |
| * * * RETRACTION ON 11/24/99 AT 1907 EST FROM THOMAS J. LANDIN TAKEN BY |
| MACKINNON * * * |
| |
| Further evaluation of this condition by engineering has determined that this |
| condition is not reportable. If HPCS was called to function in accordance |
| with its design safety function while the 1E22-F012 minimum flow valve was |
| left open, HPCS injection flow would have been reduced. The engineering |
| evaluation shows that the reduction of HPCS system flow caused by the |
| minimum flow valve open would not compromise the safety function of HPCS |
| system. That is, even with the minimum flow valve wide open, HPCS could |
| still perform its safety function and designed RCIC backup function. |
| Therefore, there is no reportability under 10CFR50.72(b)(2)(iii)(D), and |
| this report is being retracted. |
| |
| The NRC resident inspector was notified of this event retraction by the |
| licensee. The R3DO (Gardner) was notified by the NRC operations officer. |
| |
| * * * UPDATE ON 12/01/99 AT 1016ET FROM GREG HALVERSON TAKEN BY MACKINNON |
| * * * |
| |
| On November 30, 1999, Clinton Power Station (CPS) recognized that the |
| General Electric CPS- specific SAFER/GESTR Sensitivity Study utilized a |
| methodology that is not currently established or approved in the CPS |
| Licensing Basis for evaluating ECCS cooling performance. Upon recognizing |
| that the method was not consistent with the current licensing basis, CPS |
| reassessed the event and determined that the notification should not have |
| been retracted but instead revised to report the outside design basis |
| condition described above. The decision to make the unretraction of this |
| event was made today at 0835CT. |
| |
| The NRC Resident Inspector was notified by the licensee. NRC Region 3 Duty |
| Officer (Jeff Wright) was notified of this update by the NRC Operation |
| Officer. |
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|Power Reactor |Event Number: 36476 |
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| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 12/01/1999|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 03:24[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 12/01/1999|
+------------------------------------------------+EVENT TIME: 02:19[CST]|
| NRC NOTIFIED BY: JENKINS |LAST UPDATE DATE: 12/01/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DALE POWERS R4 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |99 Power Operation |
| | |
| | |
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EVENT TEXT
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| TECHNICAL SPECIFICATION REQD SHUTDOWN DUE TO FAILED TRAIN "A" ESFAS AFW |
| ACTUATION LOGIC RELAY 48 VDC POWER SUPPLY. |
| |
| BALANCE OF PLANT ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) |
| AUTOMATIC LOGIC RELAYS FOR AUXILIARY FEEDWATER 48 VDC TRAIN "A" POWER SUPPLY |
| FAILED. TECHNICAL SPECIFICATION 3.3.2, FUNCTION 6.C, ACTION 21, WAS ENTERED |
| AT 0117CT. AT 0119 CT THE LICENSEE ENTERED AND COMMENCED A TECHNICAL |
| SPECIFICATION REACTOR SHUTDOWN. REACTOR POWER IS BEING REDUCED AT LESS THAN |
| 0.5% PER MINUTE. TRAIN "B" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP AND THE |
| TURBINE DRIVEN AUXILIARY FEEDWATER PUMP ARE FULLY OPERABLE. THE FAILURE OF |
| THE 48 VDC POWER SUPPLY CAUSED THE BISTABLE TO CAUSE A FUEL BUILDING |
| ISOLATION SIGNAL, CONTROL ROOM ISOLATION VENTILATION SIGNAL, AND CONTAINMENT |
| PURGE ISOLATION SIGNAL ACTUATIONS. THE EMERGENCY CORE COOLING SYSTEMS AND |
| EMERGENCY DIESEL GENERATORS ARE FULLY OPERABLE. THE ELECTRICAL GRID IS |
| STABLE. |
| |
| TWO INSTRUMENT AND CONTROL TECHNICIANS HAVE BEEN CALLED IN TO INSTALL A |
| SPARE POWER SUPPLY. THE SPARE POWER SUPPLY IN PRESENTLY IN THE RECALIBRATION |
| SHOP. THE LICENSEE PROJECTS THAT THE SPARE POWER SUPPLY SHOULD BE INSTALLED |
| BY 0430 CT AT WHICH TIME THEY WILL EXIT THE TECHNICAL SPECIFICATION REQUIRED |
| SHUTDOWN. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. |
| |
| SEE EVENT # 36474 FOR THE SAME EVENT CALLED IN BY THE LICENSEE ON 11/30/99 |
| AT 0612 ET. |
| |
| |
| * * * UPDATE AT 0617ET ON 12/01/99 BY JENKINS TAKEN BY MACKINNON * * * |
| |
| AT 0430CT TECHNICAL SPECIFICATION EXITED AFTER THE POWER SUPPLY WAS |
| REPLACED/TESTED. REACTOR POWER WAS REDUCED TO 54%. REACTOR POWER WILL BE |
| INCREASED BACK TO 100% AT 0.5% PER MINUTE. |
| |
| THE NRC RESIDENT INSPECTOR IS IN THE CONTROL ROOM AND HAS BEEN NOTIFIED OF |
| THE EVENT UPDATE BY THE LICENSEE. NRC R4DO (DALE POWERS) NOTIFIED BY THE |
| HEADQUARTERS OPERATION OFFICER. |
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|General Information or Other |Event Number: 36477 |
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| REP ORG: SLOSS INDUSTRIES CORPORATION |NOTIFICATION DATE: 12/01/1999|
|LICENSEE: SLOSS INDUSTRIES CORPORATION |NOTIFICATION TIME: 09:58[EST]|
| CITY: ALEXANDRIA REGION: 3 |EVENT DATE: 11/27/1999|
| COUNTY: STATE: IN |EVENT TIME: 03:00[CST]|
|LICENSE#: 131890402 AGREEMENT: N |LAST UPDATE DATE: 12/01/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GEOFFREY WRIGHT R3 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ROSS | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NDAM DAMAGED GAUGE/DEVICE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| SHIELDING PROBLEM ON A DENSITY GAUGE. |
| |
| A TEXAS NUCLEAR DENSITY GAUGE MODEL # 570-57157C CONTAINING Cs-137 WAS |
| MEASURING 40MR @ ONE FOOT FROM THE SOURCE (BACKGROUND @ FOUR FEET) DUE TO A |
| SHIELDING PROBLEM. NO PERSONNEL EXPOSURES HAVE OCCURRED AND THE AREA HAS |
| BEEN CORDONED OFF. TEXAS NUCLEAR PERSONNEL WILL CHANGE OUT THE SOURCE ON |
| 12/3/99. REGION 3 WAS NOTIFIED BY THE LICENSEE ON 11/29/99. |
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|General Information or Other |Event Number: 36478 |
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| REP ORG: FLORIDA DEPARTMENT OF HEALTH |NOTIFICATION DATE: 12/01/1999|
|LICENSEE: PROFESSIONAL ENGINEERING & INSPECTION|NOTIFICATION TIME: 12:50[EST]|
| CITY: JUPITER REGION: 2 |EVENT DATE: 12/01/1999|
| COUNTY: STATE: FL |EVENT TIME: [EST]|
|LICENSE#: 2940-1 AGREEMENT: Y |LAST UPDATE DATE: 12/01/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KENNETH BARR R2 |
| |SCOTT MOORE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: CHARLES ADAMS (fax) | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT - LOST TROXLER GAUGE |
| |
| A Troxler Model # 3411B moisture/density gauge (serial no. 13472) was lost |
| from the back of a pickup truck. The gauge contains one 8 mCi Cs-137 source |
| and one 40 mCi Am-241/Be source. The following narrative was submitted via |
| facsimile: |
| |
| "The gauge was in the back of a pickup proceeding down Highway A1A. The |
| tailgate came open and the bed liner and gauge fell out of the vehicle. A |
| county employee working nearby witnessed the incident. He saw a vehicle stop |
| and pick up the bed liner and another vehicle stop and pick up the gauge. |
| The Martin County Sheriff's office is working the case. Martin County |
| Emergency Management and the owner are issuing a joint press release. |
| Florida Bureau of Radiation Control is also investigating the incident." |
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Page Last Reviewed/Updated Thursday, March 25, 2021