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Event Notification Report for April 12, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/09/1999 - 04/12/1999

                              ** EVENT NUMBERS **

35562  35563  35564  35565  35566  35567  35568  35569  35570  35571  35572  35573 
35574  35575  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35562       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 04/09/1999|
|    UNIT:  [] [] [3]                 STATE:  AL |NOTIFICATION TIME: 00:51[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        04/08/1999|
+------------------------------------------------+EVENT TIME:        20:45[CDT]|
| NRC NOTIFIED BY:  TIM GOLDEN                   |LAST UPDATE DATE:  04/09/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WALTER RODGERS       R2      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI TEMPORARILY INOPERABLE                                                  |
|                                                                              |
| System Affected: During the performance of a regularly scheduled             |
| Instrumentation surveillance on the Unit 3 HPCI Steam Line Space High        |
| Temperature switches (in accordance with plant procedure 3-SR-3.3.6.1(3D))   |
| personnel noticed that a relay not tested by procedure was chattering.  The  |
| affected relay 3-RLY-073-23A-K16 was adjacent to a relay 3-RLY-073-23A-K8    |
| which was being tested by the surveillance.  While troubleshooting the cause |
| of the chattering relay,  a loose wire was found in the power supply pathway |
| for the HPCI logic circuit.  This loose wire had the potential to prevent    |
| adequate voltage being supplied to the initiation and isolation logic for    |
| the Unit 3 HPCI system.                                                      |
|                                                                              |
| Actions: The loose wire was retightened.                                     |
|                                                                              |
| Reportability: The potential for inadequate voltage being available for the  |
| HPCI logic circuit resulted in a conservative decision to declare the HPCI   |
| system inoperable. In accordance with plant procedure SPP 3.5, code of       |
| Federal Regulations 10CFR50.72/73 and NUREG 1022 Rev 1 this is reportable as |
| a 4 Hour Non-Emergency report due to any event or condition that alone could |
| have prevented the Fulfillment of the safety function of structures or       |
| systems that are needed to   (d) Mitigate the consequences of an accident.   |
| This criteria is specified in 10CFR50.72.b.2.iii as a 4 hour report and in   |
| 10CFR50.73.a.2.v as a 30 day written report.                                 |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35563       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 04/09/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 02:50[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        04/08/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        23:00[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  04/09/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |BRUCE BURGESS        R3      |
|  DOCKET:  0707002                              |ROSEMARY HOGAN       IRO     |
+------------------------------------------------+SUSAN SHANKMAN       NMSS    |
| NRC NOTIFIED BY:  KEITH VANDERPOOL             |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BULLETIN 91-01 REPORT  -  VIOLATION OF NCSA                                  |
|                                                                              |
| "ON 4/8/99, AT 2300 IT WAS DISCOVERED THAT REQUIREMENT #14 OF NCSA-0333_     |
| 015.E03 WAS NOT BEING MAINTAINED ON CELL 33-3-8 WITHIN THE X-333 PROCESS     |
| BUILDING.   REQUIREMENT #14 STATES IN PART  'IF THE MOTORS ARE OFF, EITHER   |
| THE RCW CONTROL VALVE OR THE RCW SUPPLY BLOCK VALVE SHALL BE CLOSED WITHIN 4 |
| HOURS.'   THE MOTORS WERE IN FACT OFF AND THE RCW CONTROL VALVE FAILED IN    |
| THE OPEN POSITION AND THE RCW SUPPLY VALVE WAS NOT CLOSED WITHIN 4 HOURS,    |
| THUS VIOLATING REQUIREMENT #14.   VIOLATION OF THIS REQUIREMENT CONSTITUTES  |
| A LOSS OF CONTROL "B" (MODERATION) IN THE DOUBLE CONTINGENCY MATRIX FOR      |
| CONTINGENCY EVENT B.6.b.1.   CONTROL  'A'  WHICH IS THE PASSIVE BARRIER      |
| PROVIDED BY THE                                                              |
| CONDENSER AND COOLER TUBES REMAINED IN PLACE THROUGHOUT THIS EVENT.          |
| CONTROL WAS NOT ESTABLISHED WITHIN THE 4 HOUR SPECIFIED TIME FRAME THUS      |
| MAKING THIS A 4 HOUR NRC EVENT.   CONTROL HAS BEEN ESTABLISHED AND CELL      |
| 33-3-8 IS NOW ONSTREAM. (MOTORS ON)"                                         |
|                                                                              |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35564       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 04/09/1999|
|    UNIT:  [1] [2] []                STATE:  SC |NOTIFICATION TIME: 05:15[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/09/1999|
+------------------------------------------------+EVENT TIME:        04:28[EDT]|
| NRC NOTIFIED BY:  HOLLAND                      |LAST UPDATE DATE:  04/09/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WALTER RODGERS       R2      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT ENTERED 3.0.3 DUE TO BOTH TRAINS OF CONTROL ROOM VENTILATION BEING     |
| INOPERABLE.                                                                  |
|                                                                              |
| A SPURIOUS SIGNAL ON THE CHLORINE DETECTOR ON UNIT 1 "B" TRAIN CONTROL ROOM  |
| VENTILATION INTAKE WAS RECEIVED WHILE UNIT 2 VENTILATION INTAKE WAS CLOSED.  |
| UNIT 2 CONTROL ROOM INTAKE HAD PREVIOUSLY CLOSED ON A SPURIOUS SIGNAL( SEE   |
| EVENT 35561) AND IT WAS STILL CLOSED FOR TROUBLESHOOTING.  BOTH UNITS        |
| CONTROL ROOM VENT SYSTEMS BEING CLOSED RESULTS IN THE INOPERABILITY OF BOTH  |
| TRAINS OF CONTROL ROOM VENTILATION, PLACING BOTH UNITS IN TS 3.0.3.          |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
|                                                                              |
| *** UPDATE AT 0530 BY HOLLAND TO GOULD ***                                   |
|                                                                              |
| THEY EXITED 3.0.3 AT 0526 WHEN THE "B" TRAIN WAS RESTORED TO OPERABLE        |
| CONDITION.                                                                   |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35565       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 04/09/1999|
|    UNIT:  [1] [2] []                STATE:  PA |NOTIFICATION TIME: 09:14[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        04/09/1999|
+------------------------------------------------+EVENT TIME:        08:37[EDT]|
| NRC NOTIFIED BY:  DANIEL MURRAY                |LAST UPDATE DATE:  04/09/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|10 CFR SECTION:                                 |                             |
|AENS 50.72(b)(1)(v)      ENS INOPERABLE         |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Standby      |0        Hot Standby      |
|2     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EMERGENCY SIRENS INOPERABLE                                                  |
|                                                                              |
| At 0837, the control room received a report from the Beaver County Emergency |
| Management Agency (BCEMA   911 center) that the emergency notification       |
| sirens for Beaver County were inoperable.  The computer that activates the   |
| sirens was damaged by a lightning strike.  This constitutes a major loss of  |
| emergency communications capability as listed in 10CFR50.72.(b)1.v.  Crews   |
| are working to repair the main (damaged) computer and are also working to    |
| place the backup computer in service. They expect to have the emergency      |
| sirens returned to service within 1 hour.                                    |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| *** UPDATE ON 4/9/99 @ 1431 BY SHIPE TO GOULD ***                            |
|                                                                              |
| ALL SIRENS WERE RETURNED TO SERVICE AT 1401.                                 |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE INFORMED.   R1DO (KINNEMAN) WAS NOTIFIED.     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35566       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MATERIALS TESTING CONSULTANTS        |NOTIFICATION DATE: 04/09/1999|
|LICENSEE:  MATERIALS TESTING CONSULTANTS        |NOTIFICATION TIME: 12:14[EDT]|
|    CITY:  GRAND RAPIDS             REGION:  3  |EVENT DATE:        04/09/1999|
|  COUNTY:                            STATE:  MI |EVENT TIME:        09:00[EDT]|
|LICENSE#:  21-15281-02           AGREEMENT:  N  |LAST UPDATE DATE:  04/09/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BRUCE BURGESS        R3      |
|                                                |SCOTT MOORE          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  PETE GASEWICZ                |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOST TROXLER MOISTURE/DENSITY GAUGE                                          |
|                                                                              |
| A technician, en route to a project site, encountered problems with his      |
| pickup truck approximately one mile from the company offices.  The           |
| technician was transporting a Troxler model 3430 gauge, containing one 8 mCi |
| Cs-137 source and one 40 mCi Am-241/Be source.  A second truck was sent to   |
| retrieve the technician and his equipment.  However, when the gauge was      |
| moved to the second truck, it was not properly secured to the bed of the     |
| truck, nor was the tailgate raised.  Upon arrival at the office, the         |
| technician discovered that the gauge had fallen from the truck.  The         |
| technician immediately retraced the route of travel, but did not find the    |
| gauge.  The licensee believes that a passing motorist may have picked it up. |
| The gauge was locked inside of its storage case at the time of the loss.     |
| The local police department has been contacted by the licensee.              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35567       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ROCHESTER GAS AND ELECTRIC CORP      |NOTIFICATION DATE: 04/09/1999|
|LICENSEE:  COLTEC INDUSTRIES                    |NOTIFICATION TIME: 13:50[EDT]|
|    CITY:  ROCHESTER                REGION:  1  |EVENT DATE:        04/09/1999|
|  COUNTY:                            STATE:  NY |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  04/09/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN KINNEMAN        R1      |
|                                                |VERN HODGE (FAX)     NRR     |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  WIDAY (FAX)                  |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LICENSEE REPORTED A PART 21 DEFECT ON A REPLACEMENT TURBOCHARGER         |
| SUPPLIED BY COLTEC INDUSTRIES.                                               |
|                                                                              |
| THE LICENSEE REPLACED A TURBOCHARGER(MODEL 730), SUPPLIED BY COLTEC          |
| INDUSTRIES, ON THEIR "B" EMERGENCY DIESEL GENERATOR (ALCO MODEL 16-251F) AT  |
| GINNA STATION.  IT WAS DETERMINED THAT THERE WAS A MANUFACTURING DEFICIENCY  |
| IN THE REPLACEMENT TURBOCHARGER WHICH CONSISTED OF A MISSING DRAIN PORT IN   |
| THE INTERMEDIATE CASING ON THE TURBINE END WHICH WOULD PREVENT ENGINE        |
| LUBRICATING OIL FROM BEING ABLE TO DRAIN BACK TO THE ENGINE SUMP FROM THE    |
| TURBOCHARGER SHAFT AND BEARINGS.  THIS DEFICIENCY CREATED A CONDITION WHERE  |
| ENGINE LUBE OIL WAS BEING DIRECTED INTO THE  CYLINDERS THROUGH THE EXHAUST   |
| MANIFOLD PIPING, WHICH COULD HAVE RESULTED IN SERIOUS ENGINE DAMAGE.         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35568       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 04/09/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 18:07[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        04/08/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        18:55[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  04/09/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |BRUCE BURGESS        R3      |
|  DOCKET:  0707002                              |SUSAN SHANKMAN       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  RICK LARSON                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR NRC BULLETIN 91-01 REPORT                                            |
|                                                                              |
| "At 1855 on 4/8/99, a Nuclear Criticality Safety Analysis (NCSA)             |
| PLANT033.A01 control was lost. This loss was of one control (concentration), |
| which is one contingency of a double contingency design of this NCSA.        |
| Moderation was maintained. The concentration control was lost when a surge   |
| of UF6 material at less than 1% U-235 sublimed from a cell being returned to |
| service, causing the pressure in an intermediate drum (a type of surge drum) |
| to exceed the NCSA limit of 17 psia. The highest pressure reached was 19.6   |
| psia in the drum. Actions were immediately taken to reduce the drum pressure |
| and it was returned to allowable limits within 45 minutes. The drum          |
| temperature was maintained above 220F during this excursion.                |
|                                                                              |
| "This is reportable under NRC Bulletin 91-01 24-hour criticality control.    |
| There was no loss of hazardous/radioactive material or                       |
| radioactive/radiological exposure as a result of this event."                |
|                                                                              |
| The NRC resident inspector has been informed of this notification.           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35569       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  SYNCOR INTERNATIONAL CORPORATION     |NOTIFICATION DATE: 04/09/1999|
|LICENSEE:  SYNCOR INTERNATIONAL CORPORATION     |NOTIFICATION TIME: 18:31[EDT]|
|    CITY:  COLUMBUS                 REGION:  3  |EVENT DATE:        04/08/1999|
|  COUNTY:                            STATE:  OH |EVENT TIME:        03:30[EDT]|
|LICENSE#:  04-26507-01MD         AGREEMENT:  N  |LAST UPDATE DATE:  04/09/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BRUCE BURGESS        R3      |
|                                                |SUSAN SHANKMAN       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SCOTT LANGFORD               |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAE2 20.2202(b)(2)       EXCESSIVE RELEASE      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF 185 mCi OF Tc-99m                                                    |
|                                                                              |
| The licensee reported that 185 mCi of Tc-99m (5 unit doses) was lost from    |
| the Syncor radiopharmacy facility in Columbus, OH.  The missing unit doses   |
| were contained in an ammo can which was one of eight cans in this particular |
| shipment. The driver for the shipment stated that only seven cans were       |
| located on the shelf when he arrived to pick them up; however, another       |
| driver who had picked his shipment up several minutes before stated that     |
| there were eight cans located on the shelf when he left the area.            |
|                                                                              |
| This is an access controlled facility, and the licensee believes that the    |
| can was either misplaced within the facility, inadvertently delivered to the |
| wrong customer, or disposed of as an undeliverable shipment.  The licensee   |
| will submit a written report to the NRC regarding this event.                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35570       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 04/09/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 18:46[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        04/09/1999|
+------------------------------------------------+EVENT TIME:        18:38[EDT]|
| NRC NOTIFIED BY:  DANIEL MURRAY                |LAST UPDATE DATE:  04/09/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|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       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCREPANCIES DISCOVERED IN APPENDIX R PROCEDURES                            |
|                                                                              |
| "A review associated with an Engineering fire protection self-assessment has |
| identified discrepancies in manual actions specified in select Unit 1        |
| post-fire safe shutdown procedures. Steps in these procedures require        |
| certain manual actions to be taken that have been determined to be           |
| inappropriate. Performing these actions could place Unit 1 in a condition    |
| which is outside the design basis of the Fire Protection Program involving   |
| Appendix R Safe Shutdown capability. These actions involve manually          |
| de-energizing non-essential class 1E power circuits. The intent of these     |
| actions is to turn off circuits that are not required for safe shutdown in   |
| order to eliminate the potential for circuit faults due to a postulated fire |
| that could trip out an entire AC distribution panel. However, performing     |
| these actions would result in de-energizing the power to the diesel building |
| exhaust dampers. It has been determined that the dampers revert to the       |
| closed position when their power supply is de-energized. This could have     |
| resulted in the emergency diesel generator operating with insufficient       |
| ventilation for diesel room cooling. This condition could have prevented the |
| fulfillment of the safety function of the emergency diesel generators needed |
| to satisfy the Appendix R Safe Shutdown requirements. As a result of these   |
| procedural deficiencies, the ability to mitigate the consequences of a fire  |
| event and to place the plant in a safe shutdown condition cannot be          |
| assured.                                                                     |
|                                                                              |
| "A condition report has been written to document these procedural            |
| discrepancies. The root cause and corrective actions are being addressed     |
| through the corrective action program."                                      |
|                                                                              |
| The licensee will inform the  NRC resident inspector of this notification.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35571       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: YANKEE ROWE              REGION:  1  |NOTIFICATION DATE: 04/09/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 19:13[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        04/09/1999|
+------------------------------------------------+EVENT TIME:        18:50[EDT]|
| NRC NOTIFIED BY:  MARK GILMORE                 |LAST UPDATE DATE:  04/09/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Decommissioned   |0        Decommissioned   |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NUCLEAR ALERT TELEPHONE SYSTEM INOPERABLE                                    |
|                                                                              |
| The licensee reported that the Nuclear Alert telephone, which links the      |
| plant to local police departments, is inoperable.  FTS2000 and commercial    |
| telephone service is unaffected.                                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35572       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 04/10/1999|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 07:46[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        04/10/1999|
+------------------------------------------------+EVENT TIME:        03:10[CDT]|
| NRC NOTIFIED BY:  HUSTON                       |LAST UPDATE DATE:  04/10/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE YANDELL     R4      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ESF SIGNAL INITIATED CAUSING SOME CONTAINMENT ISOLATION VALVES TO CLOSE      |
|                                                                              |
| "While performing preparations for an ENS-SWG1A bus outage the alternate     |
| supply breaker ENS-ACB04 tripped.  The bus was being supplied by this source |
| and the resultant loss of power and invalid actuation signal caused several  |
| containment isolation AOVs to close.  The containment purge system was in    |
| operation and isolated as designed. Two drain system valves (DFR-AOV102 and  |
| DER AOV127) and one sample system valve (B33-FO20) also isolated."           |
|                                                                              |
| The trip took place during a clearance procedure when an individual, in the  |
| field, opened a fuse cabinet.  The incident is being investigated.  A        |
| limited restoration of systems has been done.                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35573       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATTS BAR                REGION:  2  |NOTIFICATION DATE: 04/11/1999|
|    UNIT:  [1] [] []                 STATE:  TN |NOTIFICATION TIME: 02:46[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/11/1999|
+------------------------------------------------+EVENT TIME:        00:42[EDT]|
| NRC NOTIFIED BY:  RICK O'REAR                  |LAST UPDATE DATE:  04/11/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WALTER RODGERS       R2      |
|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     M/R        N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO CONTROL ROD DRIVE MALFUNCTION                     |
|                                                                              |
| "Watts Bar Unit 1 experienced a Manual Reactor Trip during Control Rod       |
| Testing while in Mode 3 (with Reactor shutdown for Refueling Outage).   At   |
| 0042 on 04/11/1999, the Main Control Room Crew manually opened the           |
| Reactor Trip Breakers when the Control Rod Drive system continued to         |
| withdraw Shutdown Bank A following a Manual withdrawal to 10 steps.  The     |
| rods should have stopped at 10 steps withdrawn.   This was the first in a    |
| sequence of rod withdrawals per Surveillance instruction 1-S I-85-2.         |
|                                                                              |
| "All other rods were fully inserted at the time of testing Shutdown Bank A   |
| with RCS Boron concentration at 2184 PPM.  When Shutdown Bank A continued to |
| withdraw, the SRO directed the Reactor Trip breakers to be                   |
| opened and verified all rods fully inserted.  All systems responded as       |
| expected.  The Unit remains stable in Mode 3.                                |
|                                                                              |
| "In addition, this generated a Main Feedwater Isolation Signal.  At the time |
| of the event, all feedwater lines were isolated for outage work.             |
|                                                                              |
| "At present, an investigation is in progress to determine cause of event and |
| Control Rod Testing has been suspended pending outcome of that               |
| investigation."                                                              |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35574       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 04/11/1999|
|    UNIT:  [] [2] []                 STATE:  NJ |NOTIFICATION TIME: 17:52[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/11/1999|
+------------------------------------------------+EVENT TIME:        15:54[EDT]|
| NRC NOTIFIED BY:  PETE JONES                   |LAST UPDATE DATE:  04/11/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONTAINMENT VENTILATION ISOLATION                                            |
|                                                                              |
| During the process of lifting the reactor vessel head, the containment noble |
| gas monitor (2R12A) alarmed, causing a containment ventilation isolation.    |
| The containment purge isolation valves closed as a result of the isolation.  |
| Nonessential personnel were immediately evacuated from containment, and all  |
| remaining personnel (except the crane operator) were evacuated after the     |
| reactor vessel head was placed onto its stand.  The crane operator is        |
| required to be on station in accordance with station procedures.  The        |
| licensee is analyzing samples taken from the containment atmosphere.  The    |
| NRC resident inspector will be informed of this notification by the          |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35575       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 04/11/1999|
|    UNIT:  [1] [2] []                STATE:  SC |NOTIFICATION TIME: 21:13[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/11/1999|
+------------------------------------------------+EVENT TIME:        20:21[EDT]|
| NRC NOTIFIED BY:  GARY HAMILTON                |LAST UPDATE DATE:  04/11/1999|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WALTER RODGERS       R2      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|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                                   
+------------------------------------------------------------------------------+
| CONTROL ROOM CHILLERS DECLARED INOPERABLE                                    |
|                                                                              |
| Both control room ventilation chillers were declared inoperable due to high  |
| temperature in the Standby Nuclear Service Water pond.  The system had been  |
| operating in an "operable but degraded" condition due to fouling of tubes in |
| the chiller condensers.  The engineering analysis in support of continued    |
| system operation specified a maximum Standby Nuclear Service Water pond      |
| temperature of 70F (the normal temperature limit for the pond is 91.5F).   |
| The licensee is currently attempting to cool the pond, but stated that       |
| preparations are also being made to commence a dual unit shutdown.  The NRC  |
| resident inspector will be informed of this notification by the licensee.    |
|                                                                              |
| * * * UPDATE 2148 4/11/1999 FROM HAMILTON TAKEN BY STRANSKY * * *            |
|                                                                              |
| The licensee commenced shutdowns of both units at 2120.  At 2133, the "B"    |
| control room chiller was restored to operable, and the shutdowns were        |
| terminated.  Reactor power had been decreased to 98%, and is being returned  |
| to rated.  The NRC resident inspector will be informed of this notification  |
| by the licensee.                                                             |
+------------------------------------------------------------------------------+