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Event Notification Report for January 22, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/21/1999 - 01/22/1999

                              ** EVENT NUMBERS **

35261  35275  35286  35288  35289  35290  35291  35292  35293  35294  35295  35296 
35297  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35261       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 01/14/1999|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 13:06[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        01/14/1999|
+------------------------------------------------+EVENT TIME:        09:18[EST]|
| NRC NOTIFIED BY:  MARK PALMER                  |LAST UPDATE DATE:  01/21/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP ON TRIP OF TWO OF THREE REACTOR COOLANT PUMPS AND     |
| LOSS OF TWO 6.9-kV BUSES                                                     |
|                                                                              |
| During relay calibration on the 'A' 6.9-kV non-safety bus, the bus was       |
| unexpectedly deenergized.  The 'C' 6.9-kV bus is a swing bus and was tied to |
| the 'A' 6.9-kV bus, which caused it to be deenergized also.  This caused the |
| loss of two of three reactor coolant pumps, and in turn, caused an automatic |
| reactor trip from 100% power.  All systems functioned as expected, all rods  |
| fully inserted, and auxiliary feedwater started on low steam generator level |
| as expected.  All safety systems are operable except the 'A' containment     |
| hydrogen analyzer which is out of service for planned maintenance.           |
|                                                                              |
| The exact cause of the loss of the 6.9-kV buses is currently under           |
| investigation.                                                               |
|                                                                              |
| The licensee notified the NRC Resident Inspector, the State of North         |
| Carolina, and the local county.                                              |
|                                                                              |
| ***Update on 01/21/99 at 1710 ET by Mark Ellington taken by MacKinnon***     |
|                                                                              |
| The licensee stated that they had not made an official notification to the   |
| state of North Carolina or the local counties but instead they had made      |
| courtesy calls to the state of North Carolina and the applicable counties    |
| notifying them of the reactor trip.                                          |
|                                                                              |
| The licensee also stated that 'A-SA" Containment  Hydrogen Recombiner was    |
| out of service instead of the "A" containment hydrogen analyzer.   R2DO      |
| (Chris Christensen) notified.                                                |
|                                                                              |
| The NRC resident inspector was notified of this update by the licensee.      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35275       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 01/15/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 18:08[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        01/15/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        14:10[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/21/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JIM GAVULA           R3      |
|  DOCKET:  0707002                              |JOHN SURMEIER        NMSS    |
+------------------------------------------------+FRANK CONGEL         IRO     |
| NRC NOTIFIED BY:  RICHARD LARSON               |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 4-HOUR NRC 91-01 BULLETIN NOTIFICATION INVOLVING ABANDONED EQUIPMENT IN THE  |
| X-326 PROCESS BUILDING                                                       |
|                                                                              |
| ON JANUARY 15, 1999, AT 1410 EST IT WAS DISCOVERED THAT THE X-326 PROCESS    |
| BUILDING NUCLEAR CRITICALITY APPROVALS (NCSAs)  DO NOT DESCRIBE THE          |
| OPERATION/CONTROLS FOR THE FOLLOWING ABANDONED IN PLACE EQUIPMENT:  PRODUCT  |
| PURIFICATION DISTILLATION TOWER, OLD EVACUATION JETS, OLD SO2 REACTOR, OLD   |
| PW BOOSTER CONNECTED TO CELL 25-7-15,  AND [AN] OLD FREON DEGRADER.          |
|                                                                              |
| "THIS IS REPORTABLE DUE TO NOT HAVING ANY NCSA IN PLACE FOR THIS ABANDONED   |
| EQUIPMENT.                                                                   |
|                                                                              |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                      |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT."  |
|                                                                              |
| A PRIOR NRC NOTIFICATION (EVENT #33627) WAS MADE WHICH IDENTIFIED LEGACY     |
| EQUIPMENT IN THE X-326 PROCESS BUILDING, HOWEVER, THE ABOVE EQUIPMENT WAS    |
| INADVERTENTLY OMITTED.  THE EQUIPMENT IS IN GEOMETRICALLY FAVORABLE          |
| CONDITIONS AND CONTAINS URANIUM BELOW THE SAFE MASS LIMIT.  THIS CONDITION   |
| WAS DISCOVERED IN A REVIEW OF COMPLETED NCSAs.                               |
|                                                                              |
| THE LICENSEE WILL INFORM THE DOE SITE REPRESENTATIVE AND HAS INFORMED THE    |
| NRC RESIDENT INSPECTOR.                                                      |
|                                                                              |
| * * * UPDATE AT 1955 ON 1/18/99, BY LARSON, TAKEN BY WEAVER * * *            |
|                                                                              |
| "THIS IS REPORTABLE DUE TO NOT HAVING ANY NCSA IN PLACE FOR THIS ABANDONED   |
| EQUIPMENT.                                                                   |
|                                                                              |
| UPDATE: DUE TO THE PROBLEMS CONCERNING ABANDONED EQUIPMENT IN THE X-326      |
| BUILDING NOT COVERED BY NUCLEAR CRITICALITY SAFETY APPROVALS (NCSAs), A      |
| SEARCH PERFORMED IN THE X-705 & X-700 REVEALED ABANDONED EQUIPMENT THAT MAY  |
| NEED NCSAs. THE PLANT IS FOLLOWING IT'S PROCEDURE FOR ANOMALOUS NCSA         |
| CONDITIONS AND FURTHER EVALUATIONS ARE IN PROGRESS TO DETERMINE IF THIS      |
| ABANDONED EQUIPMENT MEETS THE FISSILE MATERIAL LIMITS. THE FISSILE MATERIAL  |
| LIMIT OF 15 GRAMS U235 BY PLANT PROCEDURES REQUIRES NCSAs."                  |
|                                                                              |
| THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                       |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT.   |
|                                                                              |
| The licensee informed the NRC resident inspector.  The Operations Officer    |
| notified the RDO (Gavula); EO (Surmeier); IRO (Congel).                      |
|                                                                              |
| * * * UPDATE AT 1643 ON 1/20/99, BY HALCOMB, TAKEN BY WEAVER * * *           |
|                                                                              |
| DUE TO PROBLEMS CONCERNING ABANDONED EQUIPMENT IDENTIFIED IN THE X-326       |
| BUILDING NOT COVERED BY AN NCSA, A PLANT WIDE SEARCH WAS INITIATED TO        |
| IDENTIFY ALL EQUIPMENT WHICH MAY MEET THE FISSILE MATERIAL LIMITS AND WOULD  |
| REQUIRE AN ACTIVE NCSA. THIS SEARCH HAS IDENTIFIED THAT THE X-344, X-333,    |
| AND THE X-330 BUILDINGS CONTAIN ABANDONED EQUIPMENT THAT WILL REQUIRE AN     |
| NCSA.  ALL IDENTIFIED EQUIPMENT HAS BEEN BOUNDARIED OFF AND AN ANOMALOUS NCS |
| CONDITION REPORT COMPLETED.                                                  |
|                                                                              |
| THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                       |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT.   |
|                                                                              |
| The licensee informed the NRC resident inspector.  The Operations Officer    |
| notified the RDO (Lanksbury); EO (BELL); IRO (Congel).                       |
|                                                                              |
| ***Update on 01/21/99 at 1847 ET by Sissler taken by MacKinnon***            |
|                                                                              |
| During ongoing plant search for abandoned equipment, additional equipment    |
| was discovered in the X-326 building which may meet the fissile material     |
| limits and would require an active NCSA.  The identified equipment has been  |
| boundaried off and an anomalous NCS condition report completed.              |
|                                                                              |
| The NRC resident inspector was notified of this event by the certificate     |
| holder. The Operations Officer notified R3DO (Lanksbury) and EO (Bell) .     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35286       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD                REGION:  3  |NOTIFICATION DATE: 01/20/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 13:00[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/20/1999|
+------------------------------------------------+EVENT TIME:        11:22[CST]|
| NRC NOTIFIED BY:  BOB NORK                     |LAST UPDATE DATE:  01/21/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |ED GOODWIN           NRR     |
|AAEC 50.72(a)(1)(i)      EMERGENCY DECLARED     |ROSEMARY HOGAN       IRO     |
|                                                |CANUPP               FEMA    |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT - LOSS OF APPROXIMATELY 50% OF CONTROL ROOM ANNUNCIATORS       |
|                                                                              |
| "Loss of redundant ANNUNCIATOR Power Supplies has rendered a substantial     |
| number of safety related annunciators inoperable.  This required a GSEP      |
| notification - Unusual Event, (MU-6 - Loss of Annunciators for >= 15         |
| minutes).  Backup indications are available and increased main control board |
| monitoring has been implemented."                                            |
|                                                                              |
| The licensee has notified the NRC resident inspector.                        |
|                                                                              |
| Event #35280 involved the same equipment.                                    |
|                                                                              |
| ***UPDATE on 01/21/99 at 1450 ET by Dave Kruck taken by MacKinnon****        |
|                                                                              |
| Unusual Event terminated at 1311 CT. The annunciator system is functional.   |
| The root cause for the failure had not been completed at the time of this    |
| event update notification.  Troubleshooting and repairs of the annunciator   |
| system are continuing.   R3DO (Lanksbury),  NRR EO (Dennig), & FEMA (Canupp) |
| notified.                                                                    |
|                                                                              |
| The NRC resident inspector was been notified of this event update by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35288       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 01/21/1999|
|    UNIT:  [2] [] []                 STATE:  PA |NOTIFICATION TIME: 09:00[EST]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        01/21/1999|
+------------------------------------------------+EVENT TIME:        05:02[EST]|
| NRC NOTIFIED BY:  TODD STRAYER                 |LAST UPDATE DATE:  01/21/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STANDBY GAS TREATMENT SYSTEM MAY NOT HAVE PERFORMED INTENDED FUNCTION DUE TO |
| DAMPER PROBLEM                                                               |
|                                                                              |
| While preparing to replace the solenoid valve for Standby Gas Treatment      |
| (SBGT) System damper PO-20466 (reactor building supply to  SBGT), the damper |
| did not open when the control room hand switch was placed in the "open"      |
| position.  However, the damper did open when the pneumatic supply to the     |
| solenoid valve was isolated. This damper opens automatically upon a SBGT     |
| system initiation to provide a flow path from the Unit 2 reactor building.   |
| The SBGT system would still have had a flow path from the Unit 2 refuel      |
| floor and equipment cell exhaust areas upon an initiation.  In addition, the |
| Unit 2 refuel floor currently has direct communication with the Unit 2       |
| reactor building because the refuel floor equipment hatch is removed.        |
|                                                                              |
| The licensee reported this event because the failure of the damper to open   |
| could have prevented the SBGT system from performing its intended function.  |
| The licensee is performing calculations to determine whether the failure     |
| would have prevented the fulfillment of the safety function. The damper is   |
| currently open, and the pneumatic supply to the solenoid valve has been      |
| isolated. The licensee plans to continue activities to replace the solenoid  |
| valve.                                                                       |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35289       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 01/21/1999|
|    UNIT:  [] [2] []                 STATE:  TX |NOTIFICATION TIME: 09:50[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/21/1999|
+------------------------------------------------+EVENT TIME:        06:07[CST]|
| NRC NOTIFIED BY:  TIM FRAWLEY                  |LAST UPDATE DATE:  01/21/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DALE POWERS          R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC TURBINE/REACTOR TRIP DURING TROUBLESHOOTING                        |
|                                                                              |
| "During troubleshooting activities to isolate the source of a ground on a    |
| 480VAC load center, the power source to the main turbine trip interlocks was |
| inadvertently deenergized. As a result, the main turbine tripped, resulting  |
| in an automatic reactor trip - reactor power was above P9 (50% power). All   |
| equipment performed as expected; all control rods fully inserted, and the    |
| auxiliary feedwater system actuated automatically on low steam generator     |
| levels (expected to occur upon a reactor trip from high power levels)."      |
|                                                                              |
| The licensee also reported that several steam generator PORVs lifted         |
| following the trip; this is expected following a trip from this power level. |
| The NRC resident inspector has been informed of this event by the licensee.  |
|                                                                              |
| ***Update on 01/21/99 at 1700 ET by Frawley taken by MacKinnon***            |
|                                                                              |
| On investigation it was determined that no steam generator PORVs lifted      |
| following the reactor trip.                                                  |
| R4DO (Dale Powers) notified.                                                 |
|                                                                              |
| The NRC resident inspector will be notified of this update by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35290       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 01/21/1999|
|    UNIT:  [1] [2] []                STATE:  MN |NOTIFICATION TIME: 13:59[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        01/21/1999|
+------------------------------------------------+EVENT TIME:        12:30[CST]|
| NRC NOTIFIED BY:  DOUG SMITH                   |LAST UPDATE DATE:  01/21/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LICENSEE DETERMINED THAT CERTAIN AUXILIARY BUILDING DOORS WOULD NOT RELIEVE  |
| PRESSURE AS DESIGNED FOLLOWING A HIGH ENERGY LINE BREAK (HELB).              |
|                                                                              |
| "The Prairie Island HELB analysis assumes that certain doors open to         |
| mitigate the pressure and temperature response. A calculation to             |
| reconstitute blow out pressure of the doors in the vent path was unable to   |
| verify doors would perform their HELB assumed function of opening to         |
| mitigate auxiliary building pressures. Latch pins on the stationary side of  |
| the doors do not allow the doors to swing open when required by the HELB     |
| event. Preliminary results from the calculation indicate damage would occur  |
| to other safety related structures. The doors will be unlatched to allow     |
| this pressure release to occur bringing the plant within the analysis.       |
| Category 1 doors 134, 184, 133, and 182 were declared inoperable per TS      |
| 3.6.E.1."                                                                    |
|                                                                              |
| Both units will remain in the  24-hour TS LCO until the latch pins are       |
| removed.  Hourly fire watches are assigned while the doors are unlatched.    |
| The licensee has long-term corrective actions under review.  This condition  |
| was discovered during an on-going design review.                             |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35291       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FT CALHOUN               REGION:  4  |NOTIFICATION DATE: 01/21/1999|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 14:00[EST]|
|   RXTYPE: [1] CE                               |EVENT DATE:        01/21/1999|
+------------------------------------------------+EVENT TIME:        10:10[CST]|
| NRC NOTIFIED BY:  DAVE BANNISTER               |LAST UPDATE DATE:  01/21/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |DALE POWERS          R4      |
|10 CFR SECTION:                                 |BOB DENNIG,  NRR     EO      |
|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                                   
+------------------------------------------------------------------------------+
| 161kV incoming line declared inoperable.                                     |
|                                                                              |
| Report required by Technical Specification 2.7(2) c. as a result of          |
| declaring 161kV incoming line inoperable.  Declaring 161kV inoperable        |
| renders both house service transformers T1A3 and T1A4 inoperable (feed vital |
| onsite buses).  161kV is energized, and breakers 110 and 111 did not open,   |
| but cannot be brought back-in-house until lockout 86X/FT/161, which tripped, |
| is reset.                                                                    |
|                                                                              |
| A contractor performing modification work in the Fort Calhoun Station        |
| switchyard was trenching, and the trencher caught a cable buried             |
| approximately 4 inches underground.  This cable supplies 161kV fast transfer |
| secondary potential transformer alarm circuit.                               |
|                                                                              |
| All 4160 v  buses successfully fast transferred to the onsite 22kV power     |
| source, and Abnormal Operating Procedure AOP-31, "All 4160V Buses fed From   |
| 22kV," was entered.                                                          |
|                                                                              |
| A new cable is being run, and should be completely installed and tested by   |
| mid-afternoon, allowing transfer back to 161kV.  A relay exists that might   |
| be able to be bypassed, which would allow 161kV to be brought back into the  |
| plant.                                                                       |
|                                                                              |
| All Emergency Diesel Generators are fully operable if needed and the non-Q   |
| Auxiliary Feedwater Pump is also fully operable.                             |
|                                                                              |
| The NRC resident inspector has been notified of this event by the licensee.  |
|                                                                              |
|                                                                              |
| ****Update on 01/21/99 at 1602 ET by Bannister taken by MacKinnon****        |
|                                                                              |
|                                                                              |
| The cable damaged in the Fort Calhoun switchyard has been replaced; the      |
| lockout relay, 86X/FT/161, has been reset; and the plant is now back in its  |
| normal electrical lineup with 161kV supplying both house service             |
| transformers T1A3 and T1A4 at 1440 CT. Technical Specification 2.7.(2) c.    |
| and Abnormal Operating Procedure APO-31 were exited. R4DO (D. Powers) & NRR  |
| EO (Dennig) notified.                                                        |
|                                                                              |
| The NRC resident inspector was notified of this event update by the          |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35292       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COMMONWEALTH OF MASS                 |NOTIFICATION DATE: 01/21/1999|
|LICENSEE:  AMERSHAM                             |NOTIFICATION TIME: 14:06[EST]|
|    CITY:  Burlington               REGION:  1  |EVENT DATE:        01/21/1999|
|  COUNTY:                            STATE:  MA |EVENT TIME:        11:00[EST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  01/21/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN KINNEMAN        R1      |
|                                                |FRED COMBS, NMSS     EO      |
+------------------------------------------------+EASTON, NMSS                 |
| NRC NOTIFIED BY:  R. FAIRFULL                  |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| The following facsimile was received from Massachusetts:                     |
|                                                                              |
| "The Radiation Control Program was notified at approximately 11:00 a.m.      |
| today that a package exceeding transportation limits had been received by    |
| AEA Technology (formerly Amersham Corp.) this morning.                       |
|                                                                              |
| "The following facts were reported:                                          |
|                                                                              |
| 1. package was from their parent company in England                          |
| 2. max reading was 820 mr/hour; Transportation Index of 18                   |
| 3. package consisted of outer packaging, with styrofoam intermediate insert, |
| containing a lead pot                                                        |
| 4. lead pot contained three cesium sealed sources - total of 9 curies        |
| 5. sources were not braced within the pot                                    |
| 6. readings varied with package orientation range of 540-820 mr/hr           |
|                                                                              |
| "The Radiation Control Program dispatched an inspector to the AEA Technology |
| facility in Burlington Massachusetts this afternoon to investigate."         |
|                                                                              |
| See HOO log book for phone number.                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35293       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS           REGION:  1  |NOTIFICATION DATE: 01/21/1999|
|    UNIT:  [1] [2] []                STATE:  MD |NOTIFICATION TIME: 16:51[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        01/21/1999|
+------------------------------------------------+EVENT TIME:        15:45[EST]|
| NRC NOTIFIED BY:  UMPHREY                      |LAST UPDATE DATE:  01/21/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |JOHN KINNEMAN        R1      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PENETRATION ROOM VENTILATION SYSTEM MAY NOT PROVIDE ADEQUATE ACCIDENT        |
| MITIGATION WHILE MAINTENANCE IS PERFORMED ON SYSTEM.                         |
|                                                                              |
| Penetration room ventilation system does not provide adequate protection to  |
| control the release of radioactive material and mitigate the consequences of |
| an accident during the maintenance activities on the system due to system    |
| design.  At the present time the licensee is investigating corrective        |
| actions to be taken to corrective this problem.                              |
|                                                                              |
| The NRC resident inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35294       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  U.S. ARMY                            |NOTIFICATION DATE: 01/21/1999|
|LICENSEE:  U. S. ARMY                           |NOTIFICATION TIME: 16:57[EST]|
|    CITY:  ROCK ISLAND              REGION:  3  |EVENT DATE:        01/21/1999|
|  COUNTY:                            STATE:  IL |EVENT TIME:        14:00[CST]|
|LICENSE#:  12-00722-06           AGREEMENT:  Y  |LAST UPDATE DATE:  01/21/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ROGER LANKSBURY      R3      |
|                                                |MIKE BELL, NMSS      EO      |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TIM MOHS                     |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:                                |                             |
|10 CFR SECTION:                                 |                             |
|IBAD 30.50(b)(1)(ii)     MATL >5X LOWEST LIMIT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| U S ARMY  M137 telescope found to have tritium contamination.                |
|                                                                              |
| An M137 telescope was received at Fort Campbell, KY  on 12/21/98. The        |
| telescope outer cover was removed on 01/13/99 at which time it was found     |
| that at least one tritium vial inside the telescope was broken. Wipes taken  |
| of the telescope and the surrounding area were sent to Rock Island Arsenal,  |
| IL to be counted for tritium activity.  Today, (01/21/99), the results of    |
| the highest reading wipe was determined to be 6E06 DPM.  Nobody at this time |
| is known to have been contaminated, but bioassays of personnel who have come |
| into contact with the telescope are being or will be taken.  The telescope   |
| was shipped out of Galesburg, IL  to Macomb, IL, then from Macomb, IL to     |
| Springfield, IL. The telescope then passed through Ft. Drum, NY, and on to   |
| Fort Campbell, KY.                                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35295       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 01/21/1999|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 16:59[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        01/21/1999|
+------------------------------------------------+EVENT TIME:        15:00[CST]|
| NRC NOTIFIED BY:  RICK ROBBINS                 |LAST UPDATE DATE:  01/21/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Material for deionized water supply valve changed                            |
|                                                                              |
| During storeroom valve stock review, the licensee discovered that valve      |
| materials for a deionized water supply line containment isolation valve had  |
| changed.  Specifically, the diaphragm material had changed.  The design      |
| value for the original material was 200 F at 200 psi.  The new valve was    |
| rated at 150  F at 300 psi.  This valve inside containment and another      |
| valve outside containment are normally closed during operation.  Further     |
| evaluations are underway.                                                    |
|                                                                              |
| Containment integrity has been verified by ensuring the valve outside        |
| containment is locked shut.                                                  |
|                                                                              |
| The NRC resident inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35296       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 01/21/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 18:17[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/21/1999|
+------------------------------------------------+EVENT TIME:        14:00[EST]|
| NRC NOTIFIED BY:  ED HYNE                      |LAST UPDATE DATE:  01/21/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD  |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Emergency diesel generators, while running unloaded, may have failed to      |
| energize emergency buses in the event of a unit trip with the 115 kV supply  |
| out of service.                                                              |
|                                                                              |
| A fire in the plant's hydrogen storage facility (event # 35275 on 01/14/99)  |
| resulted in a decision to remove the 115 kV reserve power supply from        |
| service to safely suppress the fire.  The Emergency diesel generators were   |
| started per plant surveillance procedure ST-9D to demonstrate operability as |
| required by Technical Specifications. A decision was made to allow the       |
| emergency diesel generators to run unloaded for a period of time with the    |
| 115 kV reserve power out of service but available.  A later review of the    |
| emergency diesel generator  protective scheme indicates the possibility that |
| one or more of the emergency diesel generators may have failed to energize   |
| the emergency buses in the event of a unit trip with the 115 kV supply out   |
| of service.  Further evaluation of this scenario is continuing to determine  |
| any necessary procedural changes.                                            |
|                                                                              |
| The NRC resident inspector has been notified of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35297       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 01/22/1999|
|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 00:59[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/21/1999|
+------------------------------------------------+EVENT TIME:        18:25[PST]|
| NRC NOTIFIED BY:  JOSEPHINE BROWN              |LAST UPDATE DATE:  01/22/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DALE POWERS          R4      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Courtesy call regarding safeguards system degradation related to computer.   |
| Compensatory measures were taken immediately upon discovery. Refer to the    |
| HOO Log for additional details. The NRC resident inspector will be informed  |
| of this notification by the licensee.                                        |
+------------------------------------------------------------------------------+