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Event Notification Report for March 3, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/02/1999 - 03/03/1999

                              ** EVENT NUMBERS **

35384  35427  35428  35429  35430  35431  35432  35433  35434  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35384       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 02/19/1999|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 13:33[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        02/19/1999|
+------------------------------------------------+EVENT TIME:        09:51[EST]|
| NRC NOTIFIED BY:  BREADY                       |LAST UPDATE DATE:  03/02/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIM TRAPP            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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SEVERAL ESF ACTUATIONS OCCURRED DUE TO THE UNEXPECTED DE-ENERGIZATION OF THE |
| "D" 4.16KV VITAL BUS.                                                        |
|                                                                              |
| DURING THE CONDUCT OF AN 18 MONTH DEGRADED VOLTAGE TEST OF THE "D" 4.16KV    |
| VITAL BUS INFEED BREAKER, THE BUS WAS INADVERTENTLY DE-ENERGIZED RESULTING   |
| IN A BUS UNDERVOLTAGE CONDITION.  THE RELAY TECHNICIAN CONDUCTING THE TEST   |
| STATED THAT THE NORMAL INFEED BREAKER TRIPPED OPEN AS HE WITHDREW HIS        |
| VOLTMETER LEADS UPON COMPLETING THE DEGRADED VOLTAGE RELAY STATUS CHECK.     |
| THE CAUSE OF THIS BREAKER TRIP IS UNKNOWN AND BEING INVESTIGATED.  THE       |
| ALTERNATE FEED BREAKER DID NOT CLOSE WHEN THE NORMAL INFEED TRIPPED, AND THE |
| "D" VITAL BUS WAS DE-ENERGIZED AS A RESULT.  AT THE TIME OF THE EVENT, THE   |
| PLANT WAS IN OPERATIONAL CONDITION 5 WITH CORE OFF LOAD IN PROGRESS.  "A"    |
| AND "C" CHANNELS OF ELECTRICAL POWER AND SAFETY RELATED EQUIPMENT WERE       |
| PROTECTED AND AVAILABLE.  THE "D" EMERGENCY DIESEL GENERATOR HAD BEEN        |
| CLEARED AND TAGGED FOR SCHEDULED MAINTENANCE, AND THE "DD447" 125 VDC        |
| BATTERY WAS ALSO CLEARED AND TAGGED FOR SCHEDULED MAINTENANCE.  THE LOSS OF  |
| THE 4.16 KV BUS DE-ENERGIZED THE ASSOCIATED "D" CHANNEL 480 VAC UNIT         |
| SUBSTATION, MOTOR CONTROL CENTERS, AND UNINTERRUPTIBLE POWER SUPPLIES.  THE  |
| LOSS OF THIS ASSOCIATED EQUIPMENT CAUSED A LOSS OF THE CONTROL ROD POSITION  |
| INDICATION, REACTOR BUILDING VENTILATION, AND REACTOR WATER CLEANUP PUMPS.   |
| THE "A" RHR PUMP REMAINED IN SHUTDOWN COOLING AND WAS NOT AFFECTED BY THE    |
| LOSS OF THE "D" BUS.  THE FRVS SYSTEM WAS PLACED IN SERVICE TO RESTORE THE   |
| REACTOR BUILDING TO A NEGATIVE PRESSURE.  ONE OF TWO COMMON SHUTDOWN COOLING |
| SUCTION ISOLATION VALVES WAS DE-ENERGIZED IN THE OPEN POSITION, AS WELL AS   |
| THE "A" SHUTDOWN COOLING RETURN TO THE REACTOR VESSEL.  CORE ALTERATIONS     |
| WERE TERMINATED AT THE TIME OF THE EVENT, AND THERE WAS NO IMPACT TO PLANT   |
| SAFETY.  BUS RESTORATION AND ROOT CAUSE INVESTIGATION IS IN PROGRESS.        |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
|                                                                              |
|                                                                              |
| * * * UPDATE ON 3/2/99 @ 2215 BY CONICELLA TO GOULD * * *  EVENT RETRACTION  |
|                                                                              |
| THE LICENSEE HAS REVIEWED THIS EVENT AND HAS DETERMINED THAT THE SELF        |
| INDUCED UNDERVOLTAGE CONDITION ON THE BUS DID NOT ACTUATE THE  ESF EQUIPMENT |
| (DIESEL GENERATOR)  SINCE IT WAS REMOVED FROM SERVICE.  THEREFORE, THIS      |
| EVENT WAS NOT REPORTABLE AND IS BEING RETRACTED.                             |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
|                                                                              |
| THE REG 1 RDO (MODES) WAS NOTIFIED.                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35427       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE                   REGION:  2  |NOTIFICATION DATE: 03/02/1999|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 04:32[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/02/1999|
+------------------------------------------------+EVENT TIME:        02:06[EST]|
| NRC NOTIFIED BY:  LEE MANSFIELD                |LAST UPDATE DATE:  03/02/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT HAAG          R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - MANUAL Rx TRIP FROM 100% DUE TO CLOSURE OF LOOP 3 MAIN FEEDWATER ISOLATION |
| VALVE -                                                                      |
|                                                                              |
| WHILE IN THE PROCESS OF HANGING AN OUTAGE CLEARANCE TAG ON UNIT 1 EQUIPMENT  |
| (SEE EVENT #35421), PLANT TECHNICIANS ERRONEOUSLY PULLED THE FUSES TO THE    |
| UNIT 2 LOOP 3 MAIN FEEDWATER ISOLATION VALVE (#2HV-5229) TO #3 STEAM         |
| GENERATOR CAUSING THE VALVE TO CLOSE.  CONTROL ROOM OPERATORS OBSERVED THE   |
| LOW WATER LEVEL IN #3 STEAM GENERATOR AND THE STEAM FLOW/FEED FLOW MISMATCH  |
| ANNUNCIATORS.                                                                |
|                                                                              |
| AT 0206 ON 03/02/99, CONTROL ROOM OPERATORS MANUALLY TRIPPED THE REACTOR     |
| FROM 100% POWER.  ALL CONTROL RODS INSERTED COMPLETELY.  THE AUXILIARY       |
| FEEDWATER SYSTEM ACTUATED, AS EXPECTED.  STEAM IS BEING DUMPED TO THE MAIN   |
| CONDENSER.                                                                   |
|                                                                              |
| DURING THE TRIP, AN ELECTRO-HYDRAULIC CONTROL (EHC) SYSTEM POWER SUPPLY      |
| FAILED CAUSING ERRONEOUS INDICATIONS OF MAIN CONDENSER VACUUM AND EHC        |
| PRESSURE.                                                                    |
|                                                                              |
| UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY).                                    |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35428       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 03/02/1999|
|    UNIT:  [1] [2] []                STATE:  MI |NOTIFICATION TIME: 13:14[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/02/1999|
+------------------------------------------------+EVENT TIME:        09:20[EST]|
| NRC NOTIFIED BY:  KOSLOFF                      |LAST UPDATE DATE:  03/02/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ICE CONDENSER DESIGN BASIS BYPASS FLOW COULD BE EXCEEDED FOLLOWING A STEAM   |
| LINE RUPTURE AND STRUCTURAL FAILURE IN THE STEAM GENERATOR COMPARTMENT.      |
|                                                                              |
| "This is Don Kosloff at American Electric Power, DC Cook Plant, calling with |
| a notification under 10CFR50.72 (b)(2)(i), a condition which was found while |
| the reactor was shutdown, which if it had been found while the reactor was   |
| operating, would have resulted in the nuclear power plant being in an        |
| unanalyzed condition, outside the design basis.                              |
|                                                                              |
| "The Cook units are pressurized water reactors with ice condenser            |
| containments. The ice condenser containment requires that the steam and air  |
| flowing from the lower containment compartment in the event of an accident   |
| be routed to the upper containment compartment through the ice condenser ice |
| bed. To accomplish this, a structural barrier, called the divider barrier,   |
| separates the lower and upper containment compartments. The divider barrier  |
| includes the walls of the ice compartment, the upper deck, the gates         |
| separating the reactor cavity from the refueling canal, portions of the      |
| walls of the refueling canal, and the compartments enclosing the upper       |
| portion of the steam generators and pressurizer.                             |
|                                                                              |
| "The design basis limits bypass flow around the ice bed to no more than 5    |
| square feet. For Unit 1, the installed bypass through the refueling cavity   |
| drains is equivalent to 2.2 square feet plus approximately 0.36 square feet  |
| bypass via the backdraft damper of the air return fans, totaling 2.56 square |
| feet of bypass area. The construction of Unit 2 is similar. On August 12,    |
| 1998, it was determined that the cumulative bypass area for unit 1, had been |
| equivalent to 5.71 square feet.  This condition was reported on September    |
| 11,1998 in LER 50-315/98-037. During a recent review of existing structural  |
| design calculations, AEP personnel determined that there was a potential for |
| a steam line break to overstress the associated steam generator compartment. |
| Such a steam line break inside a steam generator compartment could cause an  |
| additional bypass opening through the reinforced concrete walls of the       |
| compartment. Such an opening would increase the cumulative effective bypass  |
| opening. The size of such an opening has not been determined. Therefore, the |
| safety significance of this potential condition cannot yet be determined.    |
| Additional calculations are planned."                                        |
|                                                                              |
| The resident inspector has been informed.                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35429       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 03/02/1999|
|    UNIT:  [1] [2] []                STATE:  MI |NOTIFICATION TIME: 14:17[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/02/1999|
+------------------------------------------------+EVENT TIME:        13:52[EST]|
| NRC NOTIFIED BY:  KOSLOFF                      |LAST UPDATE DATE:  03/02/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|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        Cold Shutdown    |0        Cold Shutdown    |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Plant reported a loss of emergency response capability.                      |
|                                                                              |
| The Emergency Operations Facility requires three shifts of personnel. Each   |
| shift requires 7 communicators. All 21 communicators participated in EP      |
| drills. However, only 5 of the 21 have completed qualification               |
| documentation. Should an event occur that requires use of the EOF, the EP    |
| supervisor will mentor the unqualified communicators. An additional          |
| corrective action will be reinstatement of individuals previously qualified. |
| Both Units are currently in Mode 5.                                          |
|                                                                              |
|                                                                              |
| The Resident Inspector was informed.                                         |
|                                                                              |
|                                                                              |
| *** UPDATE ON 3/2/99 @ 2240 BY DEPUYDT TO GOULD ***                          |
|                                                                              |
| THIS UPDATE IS TO CLARIFY THE INITIAL INFORMATION PROVIDED.                  |
|                                                                              |
| EACH EOF "TEAM" HAS 12 CRITICAL POSITIONS.  OF THESE 12 POSITIONS, 7 ARE     |
| COMMUNICATOR POSITIONS.  FOR THE 3 EOF TEAMS THAT COOK HAS, A TOTAL OF 21    |
| QUALIFIED COMMUNICATORS ARE REQUIRED.                                        |
|                                                                              |
| CURRENTLY, THEY HAVE ONLY 5 FULLY QUALIFIED COMMUNICATORS OUT OF THE         |
| REQUIRED 21, AND OF THOSE 5, FOUR ARE ALL QUALIFIED FOR THE SAME POSITION.   |
|                                                                              |
|                                                                              |
| THEREFORE, DUE TO THE SHORTAGE OF QUALIFIED COMMUNICATORS TO MAN THE         |
| REQUIRED CRITICAL POSITIONS, THE EOF CANNOT BE MANNED WITH A FULL TEAM OF    |
| QUALIFIED INDIVIDUALS.  AS AN INTERIM ACTION, SHOULD AN EVENT OCCUR THAT     |
| REQUIRES THE ACTIVATION OF THE EOF, THE INDIVIDUALS CURRENTLY ON THE CALL    |
| OUT LIST FOR THOSE COMMUNICATOR POSITIONS WOULD BE CALLED OUT AND THE        |
| EMERGENCY PLANNING SUPERVISOR WOULD MENTOR THOSE UNQUALIFIED INDIVIDUALS IN  |
| THEIR DUTIES.                                                                |
|                                                                              |
| WITHIN THE NEXT 24 HOURS, CORRECTIVE ACTION WILL BE IMPLEMENTED BY           |
| REQUALIFICATION AND REINSTATEMENT OF THE INDIVIDUALS WHO WERE PREVIOUSLY     |
| QUALIFIED FOR THE COMMUNICATOR POSITIONS.                                    |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
|                                                                              |
| THE REG 3 RDO(CREED) WAS NOTIFIED.                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35430       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  STATE OF FLORIDA BUREAU OF RAD. CTL  |NOTIFICATION DATE: 03/02/1999|
|LICENSEE:  FLORIDA DEPT OF TRANSPORTATION       |NOTIFICATION TIME: 15:10[EST]|
|    CITY:  DELAND                   REGION:  2  |EVENT DATE:        03/02/1999|
|  COUNTY:                            STATE:  FL |EVENT TIME:        14:15[EST]|
|LICENSE#:  0109-1                AGREEMENT:  Y  |LAST UPDATE DATE:  03/02/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CAUDLE JULIAN        R2      |
|                                                |FRED COMBS           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ADAMS                        |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| A SOIL MOISTURE DENSITY GAUGE INVOLVED IN A MAJOR VEHICLE ACCIDENT.          |
|                                                                              |
| A TROXLER GAUGE MODEL # 3440 (SERIAL #21764 CONTAINING 8 mCi OF Cs-137 AND   |
| 40 mCi OF                                                                    |
| Am-241:Be) WAS TRANSPORTED IN A VEHICLE THAT WAS INVOLVED IN A MAJOR TRAFFIC |
| ACCIDENT INVOLVING 3 FATALITIES.  THERE WAS NO APPARENT DAMAGE TO THE GAUGE  |
| AND ITS CASE.  THE GAUGE WILL BE LEAK TESTED AND RESULTS WILL BE FORWARDED   |
| TO THE STATE RADIATION CONTROL OFFICE.  THERE MAY BE MEDIA INTEREST.         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35431       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ARKANSAS DEPT OF HEALTH RAD CONTROL  |NOTIFICATION DATE: 03/02/1999|
|LICENSEE:                                       |NOTIFICATION TIME: 17:23[EST]|
|    CITY:  WEST MEMPHIS             REGION:  4  |EVENT DATE:        03/02/1999|
|  COUNTY:                            STATE:  AR |EVENT TIME:             [CST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  03/02/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BILL JONES           R4      |
|                                                |CAUDLE JULIAN        R2      |
+------------------------------------------------+WAYNE HODGES         NMSS    |
| NRC NOTIFIED BY:  SNELLINGS                    |DON COOL             NMSS    |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TROXLER GAUGE FOUND IN SHOPPING MALL IN WEST MEMPHIS ARKANSAS                |
|                                                                              |
| A PRIVATE CITIZEN FOUND A TROXLER GAUGE MODEL 3411B AT A SHOPPING MALL IN    |
| WEST MEMPHIS, ARKANSAS.  THE CITIZEN REPORTED IT TO THE POLICE AND THE WEST  |
| MEMPHIS FIRE DEPT HAZMAT TEAM RESPONDED TO THE MALL.  THE GAUGE, WHICH       |
| BELONGED TO A TENNESSEE LICENSEE, WAS TURNED INTO THE ARKANSAS DIVISION OF   |
| RADIATION CONTROL.  THE STATE OF TENNESSEE DEPARTMENT OF RADIOLOGICAL HEALTH |
| HAS BEEN NOTIFIED BY THE DIVISION OF RADIATION CONTROL OF THE  ARKANSAS      |
| DEPARTMENT OF HEALTH.  TENNESSEE WILL HAVE THEIR LICENSEE RETRIEVE THE GAUGE |
| FROM THE ARKANSAS DIVISION OF RADIATION CONTROL.  THERE APPEARED TO BE NO    |
| DAMAGE TO THE GAUGE OR ITS CASE AND NO ABNORMAL RADIATION LEVELS WERE        |
| MEASURED.  THERE WILL BE MEDIA INTEREST.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35432       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HADDAM NECK              REGION:  1  |NOTIFICATION DATE: 03/02/1999|
|    UNIT:  [1] [] []                 STATE:  CT |NOTIFICATION TIME: 17:24[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        03/02/1999|
+------------------------------------------------+EVENT TIME:        17:17[EST]|
| NRC NOTIFIED BY:  PIONTKOWSKI                  |LAST UPDATE DATE:  03/02/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHAEL MODES        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          N       0        Decommissioned   |0        Decommissioned   |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| A POTENTIAL ERROR WITH THE DOSE TO CONTROL ROOM PERSONNEL WAS IDENTIFIED     |
|                                                                              |
| CR-99-0127 IDENTIFIES A POTENTIAL ERROR WITH THE DOSE TO CONTROL ROOM        |
| PERSONNEL DURING A POSTULATED RESIN FIRE ACCIDENT AS DESCRIBED IN THE        |
| LICENSEE'S UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR).  THE MAXIMUM ORGAN  |
| DOSE REPORTED IN THE UFSAR (SECTION 6.4.4.1) IS 3.83 REM FOR BONE.  USING    |
| THE SAME CONSERVATIVE SOURCE-TERM ASSUMPTIONS GIVEN IN THE UFSAR AND THE     |
| DOSE CONVERSION FACTORS FROM FEDERAL GUIDANCE REPORT 11, THE PRELIMINARY     |
| RECALCULATED DOSE IS 54 REM CDE (BONE) AND 3.2 REM CEDE.  THE 54 REM BONE    |
| DOSE EXCEEDS THE 50 REM LIMIT PRESCRIBED IN 10CFR50 APPENDIX A, GENERAL      |
| DESIGN CRITERION (GDC) 19, "CONTROL ROOM."                                   |
|                                                                              |
| THIS ERROR IS SPECIFIC TO THE CALCULATED CONTROL ROOM DOSE FROM THE RESIN    |
| FIRE ACCIDENT SCENARIO.  A SIMILAR ANALYSIS WAS PERFORMED FOR THE RESIN FIRE |
| ACCIDENT SCENARIO TO CALCULATE THE OFFSITE DOSE TO MEMBERS OF THE PUBLIC.    |
| THIS CALCULATION USED A DIFFERENT METHODOLOGY THAN THE CONTROL ROOM DOSE     |
| ANALYSIS AND HAS BEEN VERIFIED.                                              |
|                                                                              |
| IF THE PLANT OPERATED AS PRESENTLY ALLOWED, THE POTENTIAL EXPOSURE TO        |
| CONTROL ROOM OPERATORS COULD EXCEED THE DESIGN BASIS OF GDC 19 FOR THE       |
| LIMITING RADIOLOGICAL                                                        |
| EVENT, A SPENT RESIN FIRE.  IN ACTUAL PRACTICE, THE REQUIRED RADIOACTIVE     |
| CONTENT OF RESIN DOES NOT EXIST AT ANY ONE PLACE ON SITE, THEREFORE, AN      |
| ACTUAL EVENT EXCEEDING THE GDC 19 CRITERIA IS NOT CURRENTLY POSSIBLE.        |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE INFORMED.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35433       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  INTERNATIONAL PAPER CO.              |NOTIFICATION DATE: 03/02/1999|
|LICENSEE:  INTERNATIONAL PAPER CO               |NOTIFICATION TIME: 17:52[EST]|
|    CITY:  LOCK HAVEN               REGION:  1  |EVENT DATE:        03/02/1999|
|  COUNTY:                            STATE:  PA |EVENT TIME:        15:00[EST]|
|LICENSE#:  GL1933-70             AGREEMENT:  N  |LAST UPDATE DATE:  03/02/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MICHAEL MODES        R1      |
|                                                |WAYNE HODGES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  LAIRD                        |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LICENSEE IS MISSING A CONSISTENCY GAUGE FOR A PAPER MACHINE              |
|                                                                              |
| THE GAUGE, NDC SYSTEMS MODEL # 104, CONTAINS 80 MILLICURIES OF AM-241 AND IS |
| USUALLY MOUNTED TO THE PAPER MACHINE.  IT WAS LAST INVENTORIED 6 MONTHS AGO  |
| WHEN IT WAS LOCATED IN A BOX IN ONE OF THEIR OFFICES.  THEY MAY BE ABLE TO   |
| LOCATE IT WHEN THEY CAN CONTACT AN EMPLOYEE WHO MAY KNOW WHERE IT IS.        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35434       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 03/02/1999|
|    UNIT:  [] [2] []                 STATE:  WI |NOTIFICATION TIME: 18:21[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        03/02/1999|
+------------------------------------------------+EVENT TIME:        16:45[CST]|
| NRC NOTIFIED BY:  SHORT                        |LAST UPDATE DATE:  03/02/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES CREED          R3      |
|10 CFR SECTION:                                 |                             |
|ADEG 50.72(b)(1)(ii)     DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       1        Startup          |1        Startup          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUXILIARY FEEDWATER LEAKING BACK INTO MAIN FEEDWATER SYSTEM                  |
|                                                                              |
| THE LICENSEE DISCOVERED THAT THE AUXILIARY FEEDWATER SYSTEM WAS LEAKING BACK |
| INTO THE MAIN FEED SYSTEM ("B" FEED LINE) PAST TWO IN-SERIES CHECK VALVES.   |
| THESE CHECK VALVES ARE CONSIDERED CONTAINMENT ISOLATION VALVES.  LEAKAGE IS  |
| IN EXCESS OF THEIR ALLOWABLE LIMITS.  AUXILIARY FEEDWATER IS CURRENTLY       |
| FEEDING THE STEAM GENERATORS.  THE LEAKAGE HAS BEEN ISOLATED USING MANUAL    |
| VALVES.  THE UNIT WAS IN STARTUP FOLLOWING A REFUELING OUTAGE WHEN THE       |
| CONDITION WAS FOUND.                                                         |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
+------------------------------------------------------------------------------+