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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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                                   
+------------------------------------------------------------------------------+
| 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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