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Event Notification Report for November 8, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/05/1999 - 11/08/1999

                              ** EVENT NUMBERS **

36287  36364  36400  36401  36402  36403  36404  36405  36406  36407  36408  36409 
36410  36411  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36287       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 10/13/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 16:00[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/13/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        00:10[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  11/05/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |JOHN MADERA          R3      |
|  DOCKET:  0707001                              |SCOTT MOORE          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  WALKER                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| At 0010 on 10/13/99, the PSS office was notified that a primary condensate   |
| alarm was received on the C-360 position 4 autoclave Water Inventory Control |
| System (WICS). The WICS system is required to be operable while heating in   |
| mode 5 according to TSR 21.4.3. The autoclave was checked according to the   |
| alarm response procedure and subsequently removed from service and declared  |
| inoperable by the Plant Shift Superintendent.                                |
| Troubleshooting was initiated and is continuing in order to determine the    |
| reason for the alarm.                                                        |
|                                                                              |
| The NRC senior resident has been notified of this event.                     |
|                                                                              |
| * * * UPDATE 2220EST ON 11/5/99 FROM E.G. WALKER TO S. SANDIN * * *          |
|                                                                              |
| "On 11/2/99, the same type of actuation occurred on the C-360 autoclave No.  |
| 1 while out of service and open. While investigating this invalid actuation, |
| it was discovered that the gain adjustment on one of the WICS channels had   |
| drifted out of tolerance.  Discussions with the component manufacturer       |
| 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 actuation on 10/13/99 was caused by   |
| [an] invalid signal (instrument drift) and thus does not meet the criteria   |
| for reporting and should be retracted."                                      |
|                                                                              |
| The NRC resident has been notified of this retraction.  Notified             |
| R3DO(Creed).                                                                 |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36364       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 10/28/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 16:16[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/27/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        17:05[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  11/05/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MIKE JORDAN          R3      |
|  DOCKET:  0707001                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  W.F. CAGE                    |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Safety System Actuation                                                      |
|                                                                              |
| At  1705 CDT on 10/27/99, the Plant Shift Superintendent's (PSS) office was  |
| notified that a primary condensate alarm was received on the C-360 position  |
| 2 autoclave Water Inventory Control (WIC) System.  The WIC 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 declared inoperable by the PSS. 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 criteria J.2, Safety System actuation  |
| due to a valid signal as a 24-hour event notification.                       |
|                                                                              |
| The NRC resident inspector has been notified.                                |
|                                                                              |
| * * * UPDATE 2220EST ON 11/5/99 FROM E.G. WALKER TO S. SANDIN * * *          |
|                                                                              |
| "On 11/2/99, the same type of actuation occurred on the C-360 autoclave No.  |
| 1 while out of service and open. While investigating this invalid actuation, |
| it was discovered that the gain adjustment on one of the WICS channels had   |
| drifted out of tolerance.  Discussions with the component manufacturer       |
| 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 actuation on 10/27/99 was caused by   |
| [an] invalid signal (instrument drift) and thus does not meet the criteria   |
| for reporting and should be retracted."                                      |
|                                                                              |
| The NRC resident inspector has been notified of this retraction.  Notified   |
| R3DO(Creed).                                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36400       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 11/05/1999|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 04:07[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        11/04/1999|
+------------------------------------------------+EVENT TIME:        20:30[CST]|
| NRC NOTIFIED BY:  RICK ROBBINS                 |LAST UPDATE DATE:  11/05/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 0.25 INCH LONG CRACK WAS FOUND ON "1A" STEAM GENERATOR HEAD DRAIN VALVE.     |
|                                                                              |
| During a liquid penetrant examination of a weld on the top side of valve     |
| 1R-526A, the '1A' Steam Generator head drain, a 0.25" long crack was found.  |
| This appears to be a crack in the weld metal only, through wall of the       |
| Reactor Coolant System pressure boundary.                                    |
|                                                                              |
| During initial screening of this condition at 2030 hours on 11/04/99 it was  |
| not considered seriously degraded as no leak was detected while at power     |
| (boric acid crystals were found in the vicinity of the valve).  Upon further |
| review at 0200 hours on 11/05/99 this 4 hour non-emergency report was made.  |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36401       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 11/05/1999|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 05:21[EST]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        11/05/1999|
+------------------------------------------------+EVENT TIME:        02:32[CST]|
| NRC NOTIFIED BY:  TIM SMITH                    |LAST UPDATE DATE:  11/05/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|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       97       Power Operation  |97       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STEAM GENERATOR BLOWDOWN ISOLATION VALVES CLOSED                             |
|                                                                              |
| At 0232 on 11/05/99 steam generator liquid radiation monitor R-19  failed.   |
| This failure caused the following valves to close: BT-2A/MV-32077, steam     |
| generator blowdown isolation valve A1; BT-2B/MV-32079, steam generator       |
| blowdown isolation valve B1; BT-3A/MV-32078, steam generator blowdown        |
| isolation valve A2; and BT-3B/MV-32080, steam generator blowdown isolation   |
| valve B2.  These valves have a containment isolation function for a main     |
| steam line rupture within containment.  Their post - Loss of Coolant         |
| Accident function is to provide steam generator isolation.                   |
|                                                                              |
| The monitor failure will not allow the re-establishment of steam generator   |
| blowdown flow.  Plant chemistry and instrument and control personnel have    |
| been contacted to determine corrective actions and to repair the radiation   |
| monitor.  Radiation monitor R-15, Air Ejector Exhaust, is indicating normal  |
| readings and is being monitored by operations.  Local indication of          |
| radiation monitor R-19 are the normal count rate. The actual problem appears |
| to be that the Control Room indication for R-19 has failed.                  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36402       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 11/05/1999|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 11:14[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        11/05/1999|
+------------------------------------------------+EVENT TIME:        10:00[CST]|
| NRC NOTIFIED BY:  BOB MURRELL                  |LAST UPDATE DATE:  11/05/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 60% THROUGH WALL CRACK DISCOVERED DURING AN ULTRASONIC EXAMINATION           |
|                                                                              |
| While performing ultrasonic examination of recirculation riser weld RRB-F002 |
| (nozzle to safe-end weld) indications that are indicative of intragranular   |
| stress-corrosion cracking (IGSCC) were identified.  Specifically, a 60%      |
| through wall crack was found on the "B" recirculation riser nozzle to        |
| safe-end weld. This weld was replaced in 1978. The licensee will take review |
| the codes and expand the scope of work as appropriate.                       |
|                                                                              |
| The NRC resident inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36403       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 11/05/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 11:51[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        11/05/1999|
+------------------------------------------------+EVENT TIME:        10:51[EST]|
| NRC NOTIFIED BY:  ZAREMBA                      |LAST UPDATE DATE:  11/05/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       85       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TURBINE TRIP/REACTOR SCRAM ON "1B" MOISTURE SEPARATOR REHEATER HIGH WATER    |
| LEVEL.                                                                       |
|                                                                              |
| Turbine trip resulted in Reactor scram. Turbine trip was a result of a high  |
| level alarm in the "1B" Moisture Separator Reheater.  Just prior to the      |
| turbine trip there appears to have been a level transient in the "4B"        |
| feedwater heater.  All control rods fully inserted into the core. Reactor    |
| Feedwater Pumps tripped on High Reactor Vessel Water Level.  A Reactor       |
| Feedwater Pump was restarted when Reactor Vessel Water level decreased and   |
| is currently maintaining Reactor Vessel Water Level.  The Main Condenser is  |
| being used as the heat sink.  No Emergency Core Cooling Systems started as a |
| result of the turbine trip/Reactor scram.  The offsite electrical grid is    |
| stable, and the Emergency Diesel Generators are fully operable if needed.    |
|                                                                              |
| The Licensee is investigating what caused the level transient in the "4B"    |
| feedwater heater.                                                            |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36404       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 11/05/1999|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 13:28[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        11/05/1999|
+------------------------------------------------+EVENT TIME:        10:50[EST]|
| NRC NOTIFIED BY:  MICHAEL WILLIAMS             |LAST UPDATE DATE:  11/05/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PIERCE SKINNER       R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Unit 1 was manually scrammed following the unplanned trip of the "1B"        |
| Reactor Feed Pump during monthly surveillance testing.                       |
|                                                                              |
| "On November 5,1999 at 1050 [hours] a manual Reactor Scram was inserted on   |
| Unit 1 after Reactor Feed Pump '1B'  tripped during feed pump testing and    |
| Reactor Water Level was not maintained by the '1A' Reactor Feed Pump.        |
| Primary Containment Groups 2, 6 and 8 Isolations were received following the |
| manual reactor scram from low Reactor Water Level. There is normally a level |
| transient following a reactor scram, which is anticipated by the operating   |
| crew.  Reactor Water Level lowered to 112 inches.  The High Pressure Coolant |
| Injection system was manually started, but was not used for injection.   All |
| required Isolations occurred as a result of the Reactor Water Level Low      |
| Level One initiation signal.  Group 2 isolation valves include Drywell       |
| Equipment and Floor Drain, Traversing Incore Probe, Residual Heat Removal    |
| (RHR) Discharge Isolation to Radwaste and RHR Process Sampling Valves.       |
| Group 6 isolation valves include Containment Atmosphere Control System and   |
| Post Accident Valves.  Group 8 isolation valves include RHR System Shutdown  |
| Cooling Isolation Valves, these valves were closed prior to the isolation    |
| sign.                                                                        |
|                                                                              |
| "[The initial safety significance is] minimal, all systems functioned as     |
| designed.  The licensee took conservative action to insert a manual Reactor  |
| Scram.                                                                       |
|                                                                              |
| "The cause of the '1B' Reactor Feed Pump trip will be determined and         |
| corrected."                                                                  |
|                                                                              |
| All rods fully inserted.  Decay heat is being removed via the Main           |
| Condenser.  The automatic reactor scram level setpoint is 162 inches with    |
| HPCI injection occurring at 108 inches.                                      |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36405       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ILLINOIS DEPT OF NUCLEAR SAFETY      |NOTIFICATION DATE: 11/05/1999|
|LICENSEE:                                       |NOTIFICATION TIME: 17:06[EST]|
|    CITY:                           REGION:  3  |EVENT DATE:        11/01/1999|
|  COUNTY:                            STATE:  IL |EVENT TIME:        16:00[CST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  11/05/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JAMES CREED          R3      |
|                                                |WAYNE HODGES         NMSS    |
+------------------------------------------------+FRANK CONGEL         IRO     |
| NRC NOTIFIED BY:  BRUCE SANZA                  |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING INDIVIDUAL RECEIVING > 5X ANNUAL LIMIT ON   |
| INTAKE (ALI) OF TRITIUM (INHALATION)                                         |
|                                                                              |
| AT 1645 HOURS ON 11/2/99, THE ILLINOIS DEPARTMENT OF NUCLEAR SAFETY WAS      |
| INFORMED THAT AN INDIVIDUAL HAD SMASHED A TUBE ON 11/1/99 CONTAINING 2       |
| CURIES TRITIUM FROM A  SELF-POWERED EXIT SIGN INSIDE HIS RESIDENTIAL GARAGE. |
| THIS QUANTITY EXCEEDS 5X THE  (ALI) OF 10CFR20 APPENDIX B (1 ALI  INHALATION |
| IS  80 mCi).  THE REMAINING THREE TUBES WERE SAFELY REMOVED FROM THE         |
| INDIVIDUAL'S GARAGE.  THE INDIVIDUAL INITIALLY CONTACTED A POISON HOTLINE    |
| AND WAS REFERRED.  INSPECTORS FROM THE STATE AGENCY HAVE SURVEYED THE GARAGE |
| AND ARE FOLLOWING UP.                                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36406       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 11/05/1999|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 19:24[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        11/05/1999|
+------------------------------------------------+EVENT TIME:        16:40[EST]|
| NRC NOTIFIED BY:  RICHARD MESSINA              |LAST UPDATE DATE:  11/05/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     R1      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| 24-HOUR FITNESS FOR DUTY REPORT INVOLVING CONTRACTOR SUPERVISOR EMPLOYEE     |
|                                                                              |
| CONTRACTOR SUPERVISOR EMPLOYEE CONFIRMED POSITIVE FOR COCAINE FOLLOWING      |
| RANDOM DRUG TESTING.  THE INDIVIDUAL'S ACCESS HAS BEEN DENIED.  CONTACT THE  |
| HEADQUARTERS OPERATIONS CENTER FOR ADDITIONAL DETAILS.                       |
|                                                                              |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36407       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 11/06/1999|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 09:12[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        11/05/1999|
+------------------------------------------------+EVENT TIME:        15:38[CST]|
| NRC NOTIFIED BY:  RUSS GODWIN                  |LAST UPDATE DATE:  11/06/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLAUDE JOHNSON       R4      |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       90       Power Operation  |90       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR REPORT PURSUANT TO REGULATORY GUIDE 1.133                            |
|                                                                              |
| "At 1538 CST, on November 5, 1999, the River Bend Station (RBS) staff        |
| concluded that a loose part had been detected in the primary system.         |
|                                                                              |
| "The RBS staff was alerted to this condition when channel six of the Loose   |
| Parts Monitoring System (LPMS) began to alarm at approximately three to five |
| minute intervals. Channel six monitors the Feedwater 45 line. Over the      |
| remainder of the day, the alarms gradually decreased to none and there is    |
| currently no alarming condition. No other Loose Parts Monitoring channels    |
| detected this condition.                                                     |
|                                                                              |
| "The RBS staff and the LPMS vendor reviewed the data and concluded that the  |
| loose part is of relatively low mass, probably less than two pounds. The RBS |
| staff will continue to evaluate this condition.                              |
|                                                                              |
| "This report is submitted pursuant to Reg. Guide 1.133."                     |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36408       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 11/06/1999|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 21:46[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        11/06/1999|
+------------------------------------------------+EVENT TIME:        18:44[CST]|
| NRC NOTIFIED BY:  PHILLIP SHORT                |LAST UPDATE DATE:  11/06/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|AMED 50.72(b)(2)(v)      OFFSITE MEDICAL        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INJURED POTENTIALLY CONTAMINATED WORKER TRANSPORTED TO LOCAL HOSPITAL        |
|                                                                              |
| "A WORKER SLIPPED AND FELL IN THE LAUNDRY ROOM.  AN AMBULANCE WAS CALLED DUE |
| TO A POSSIBLE HIP INJURY.  A COMPLETE FRISK OF THE INDIVIDUAL WAS NOT ABLE   |
| TO BE PERFORMED PRIOR TO TRANSPORTING OFFSITE TO A LOCAL HOSPITAL.  THE      |
| INJURED PERSON IS BEING CONSIDERED POTENTIALLY CONTAMINATED.  A RADIATION    |
| PROTECTION TECHNICIAN IS ACCOMPANYING THE INJURED PERSON TO THE HOSPITAL."   |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36409       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES                REGION:  3  |NOTIFICATION DATE: 11/07/1999|
|    UNIT:  [1] [] []                 STATE:  MI |NOTIFICATION TIME: 11:56[EST]|
|   RXTYPE: [1] CE                               |EVENT DATE:        11/07/1999|
+------------------------------------------------+EVENT TIME:        09:35[EST]|
| NRC NOTIFIED BY:  HUGH NIXON                   |LAST UPDATE DATE:  11/07/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONTAINMENT SUMP SCREEN INTEGRITY QUESTIONABLE DURING A DESIGN BASIS         |
| ACCIDENT                                                                     |
|                                                                              |
| "CONTAINMENT SUMP SCREENS (ESS RECIRC) ARE IN A DIFFERENT CONFIGURATION THAN |
| PREVIOUSLY THOUGHT.  THE SCREEN MATERIAL IS NOT WELDED TO THE SCREEN FRAME   |
| FOR AT LEAST ONE THIRD OF IT'S LENGTH.  INSTEAD, THE PERIPHERY OF THE SCREEN |
| IS CLAMPED AT NUMEROUS PLACES MAKING THE SCREEN INTEGRITY QUESTIONABLE IN    |
| THE EVENT OF A DESIGN BASIS ACCIDENT FLOW RATES."                            |
|                                                                              |
| THIS CONDITION, DISCOVERED DURING THE REFUELING INSPECTION OF THE            |
| CONTAINMENT SUMP, MAY HAVE EXISTED SINCE INITIAL CONSTRUCTION.  THE LICENSEE |
| IS PERFORMING FURTHER ANALYSIS TO DETERMINE APPROPRIATE CORRECTIVE ACTIONS   |
| FOR IMPLEMENTATION PRIOR TO RESTART.                                         |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36410       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 11/07/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 15:19[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        11/07/1999|
+------------------------------------------------+EVENT TIME:        13:48[CST]|
| NRC NOTIFIED BY:  JIM McKAY                    |LAST UPDATE DATE:  11/07/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD  |                             |
|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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE DUE TO     |
| FAILURE OF THE ASSOCIATED ROOM COOLER                                        |
|                                                                              |
| "DURING NORMAL OPERATIONS, HPCI HAS BEEN DECLARED INOPERABLE IN ACCORDANCE   |
| WITH TECH SPEC SECTION 3.5.A.3.g.  HPCI IS INOPERABLE DUE TO THE FAILURE OF  |
| SUPPORT AUXILIARY EQUIPMENT, i.e., THE VENTILATION COOLING COIL HAS A MAJOR  |
| LEAK REQUIRING ISOLATION OF THE VENTILATION UNIT.  HPCI IS IN A 14-DAY       |
| LCO."                                                                        |
|                                                                              |
| THE LICENSEE WILL INFORM  STATE/LOCAL AGENCIES AS A COURTESY AND THE NRC     |
| RESIDENT INSPECTOR.                                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36411       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 11/07/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 22:36[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        11/07/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        04:00[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  11/07/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JAMES CREED          R3      |
|  DOCKET:  0707002                              |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KURT SISLER                  |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 NOTIFICATION INVOLVING LOSS OF CRITICALITY        |
| CONTROL (MODERATION)                                                         |
|                                                                              |
| "On 11/7/99 at 0400 hours, it was discovered that the standard solution used |
| to calibrate X-344, Autoclave #2 conductivity system probes on 11/1/99 was   |
| past its shelf life expiration date as stated on the certificate of NIST     |
| traceability. This brings into question the operability (AQ-NCS boundary     |
| item) of the conductivity system. Autoclave #2 was operated in Mode II       |
| (Cylinder Heating) for approximately 30 minutes on 11/2/99. Conductivity     |
| system as-found readings were performed on 11/2/99 with a standard solution  |
| in date according to NIST requirements, The as-found results were within     |
| tolerance indicating that the system would have performed its intended       |
| safety function.                                                             |
|                                                                              |
| "Nuclear Criticality Engineering has determined that the operation of the    |
| autoclave, after calibration of the conductivity system with out-dated       |
| conductivity standard solution, constitutes the loss of one (1) NCS control  |
| (moderation). The other control (Mass) was maintained throughout the         |
| duration of this event. The loss of one NCS control is reportable to the NRC |
| as a 24-hour event.                                                          |
|                                                                              |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                      |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT.   |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:                                              |
|                                                                              |
| "The safety significance of this event is low. The conductivity probes are   |
| required to be operable and are tested semi-annually to verify this. The     |
| probes were tested on 11/1/99 however, the solution used to calibrate the    |
| probes was out of date. If the probes completely failed a UF6 release in     |
| quantities greater than the minimum critical mass would have to occur or a   |
| slow release could allow a dilute UO(2)F(2) solution to reach unfavorable    |
| geometry storm drains. There was no UF6 release during this event and the    |
| autoclave was only operated for 30 minutes in this condition (As-found       |
| testing with in-date standard on 11/2/99 revealed that the conductivity      |
| system was within allowable tolerance).                                      |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW           |
| CRITICALITY COULD OCCUR):                                                    |
|                                                                              |
| "The potential pathway to criticality is that a slow UF6 release occurs      |
| (less than 2 pounds per minute) and the conductivity probes fail to detect   |
| it.  A release with greater than 2 pounds per minute would isolate the       |
| autoclave due to high pressure. This slow release could allow a dilute       |
| solution to reach unfavorable geometry storm drains.                         |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):    |
|                                                                              |
| "The controlled parameters are mass and moderation.                          |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS    |
| LIMIT AND % WORST CASE OF CRITICAL MASS):                                    |
|                                                                              |
| "The estimated amount of material is zero because there was no release, the  |
| maximum enrichment is 5% U235 and the form of material is UF6.               |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES                                              |
|                                                                              |
| "The control that was lost was moderation. The conductivity probes were      |
| calibrated with a solution that was out of date and therefore the probes     |
| were inoperable. The autoclave was operated for 30 minutes in this           |
| condition.                                                                   |
|                                                                              |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:  |
|                                                                              |
| "As found readings were completed with an in-date batch of conductivity      |
| standard solution. All as-found readings were in acceptable limits.          |
| Autoclave #2 is inoperable (since 11/4/99) for reasons other than this       |
| event."                                                                      |
|                                                                              |
| The standard solution used to calibrate the conductivity system expired on   |
| 10/12/99.  Operations has the cause for this incident report under review;   |
| however, the preliminary investigation attributes the failure to personnel   |
| error.                                                                       |
|                                                                              |
| The NRC Resident Inspector was informed.                                     |
+------------------------------------------------------------------------------+