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Event Notification Report for January 6, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/05/1999 - 01/06/1999

                              ** EVENT NUMBERS **

35155  35214  35215  35216  35217  35218  35219  35220  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35155       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 12/16/1998|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 11:07[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        12/16/1998|
+------------------------------------------------+EVENT TIME:        07:24[EST]|
| NRC NOTIFIED BY:  BOB KIDDER                   |LAST UPDATE DATE:  01/05/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN JACOBSON        R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - DIVISION 3 NORMAL BATTERY CHARGER FAILED AND WAS REPLACED BY THE RESERVE   |
| CHARGER -                                                                    |
|                                                                              |
| AT 0724 ON 12/16/98, THE CONTROL ROOM RECEIVED ANNUNCIATOR ALARMS INDICATING |
| TROUBLE ON THE DIVISION 3 DIESEL GENERATOR (DG) AND DIVISION 3 BATTERY.  BUS |
| AND BATTERY VOLTAGE HAD DECREASED FROM 129 VDC TO APPROXIMATELY 122 VDC, AND |
| THE BATTERY WAS DISCHARGING APPROXIMATELY 5 AMPS.  SUBSEQUENT INVESTIGATION  |
| DETERMINED THAT THE DIVISION 3 NORMAL BATTERY CHARGER HAD NO OUTPUT.         |
|                                                                              |
| AT 0746, PLANT OPERATORS PLACED THE DIVISION 3 DG AND THE HIGH PRESSURE CORE |
| SPRAY (HPCS) SYSTEM IN SECURE STATUS TO PREVENT A POTENTIAL AUTOMATIC        |
| INITIATION DUE TO VOLTAGE PROBLEMS AND SHIFTED THE DIVISION 3 ON-LINE        |
| BATTERY CHARGER FROM THE NORMAL BATTERY CHARGER TO THE RESERVE BATTERY       |
| CHARGER.  THE LICENSEE DECLARED THE DIVISION 3 DG AND THE HPCS SYSTEM        |
| INOPERABLE [14-DAY LIMITING CONDITION FOR OPERATION (LCO)] EVEN THOUGH THEY  |
| ARE FUNCTIONAL.                                                              |
|                                                                              |
| AT 1010, THE LICENSEE VERIFIED THE RESERVE BATTERY CHARGER AND ALL DIVISION  |
| 3 SYSTEMS TO BE OPERABLE AND EXITED THE HPCS SYSTEM LCO.                     |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND PLANS TO REPAIR/REPLACE |
| THE FAILED BATTERY CHARGER.                                                  |
|                                                                              |
| * * * UPDATE 1007 EST ON 01/05/99 FROM STERLING SANFORD TO S.SANDIN * * *    |
|                                                                              |
| THIS EVENT IS BEING RETRACTED BASED ON THE FOLLOWING:                        |
|                                                                              |
| "AFTER FURTHER REVIEW, IT HAS BEEN DETERMINED THAT THIS EVENT IS NOT         |
| REPORTABLE AS A LOSS OF SAFETY FUNCTION.  BATTERY VOLTAGE ON DIVISION 3      |
| REMAINED AT APPROXIMATELY 122 VDC.  ENGINEERING CALCULATIONS SHOW THIS       |
| VOLTAGE TO BE ABOVE THAT WHICH IS REQUIRED FOR HPCS TO PERFORM ITS SAFETY    |
| FUNCTION.                                                                    |
|                                                                              |
| "OPERATIONS CONSERVATIVELY SECURED DIVISION 3 TO ENSURE THAT NO [ENGINEERED  |
| SAFETY FEATURE] ACTUATIONS OCCURRED WHILE TRANSFERRING FROM THE NORMAL TO    |
| THE RESERVE BATTERY CHARGER.  REASONABLE OPERATOR ACTIONS COULD HAVE BEEN    |
| TAKEN TO RESTORE HPCS, IF REQUIRED.  THIS IS IN ACCORDANCE WITH NUREG-1022   |
| GUIDANCE.                                                                    |
|                                                                              |
| "DURING THIS EVENT, [AUTOMATIC DEPRESSURIZATION SYSTEM], ALL LOW-PRESSURE    |
| [EMERGENCY CORE COOLING SYSTEMS], AND [REACTOR CORE ISOLATION COOLING] WERE  |
| OPERABLE."                                                                   |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.  THE NRC OPERATIONS        |
| OFFICER NOTIFIED THE R3DO (CLAYTON).                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35214       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE               REGION:  4  |NOTIFICATION DATE: 01/05/1999|
|    UNIT:  [] [2] []                 STATE:  CA |NOTIFICATION TIME: 03:19[EST]|
|   RXTYPE: [1] W-3-LP,[2] CE,[3] CE             |EVENT DATE:        01/04/1999|
+------------------------------------------------+EVENT TIME:        20:51[PST]|
| NRC NOTIFIED BY:  HOWARD SMITH                 |LAST UPDATE DATE:  01/05/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOSEPH TAPIA         R4      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LICENSEE DETERMINED THAT THE CCW SYSTEM MAY NOT  MEET ITS REQUIREMENT TO     |
| OPERATE FOR 7 DAYS WITHOUT MAKE-UP FOLLOWING A SEISMIC EVENT.                |
|                                                                              |
| THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE:   |
|                                                                              |
| "AT SAN ONOFRE, THE COMPONENT COOLING WATER (CCW) SYSTEM IS REQUIRED TO      |
| PROVIDE COOLING FOR 7 DAYS WITHOUT MAKE-UP.  CCW TRAINS 'A' AND 'B' ARE      |
| SEISMICALLY QUALIFIED; THE NON-CRITICAL LOOP IS NOT SEISMICALLY QUALIFIED."  |
|                                                                              |
| "UNIT 2 ENTERED MODE 5 AT APPROXIMATELY 0544 PST ON JANUARY 3, 1999, FOR A   |
| PLANNED REFUELING/MAINTENANCE OUTAGE.  AT 2051 ON JANUARY 4, 1999, WHILE     |
| UNIT 2 WAS IN MODE 5, SCE DETERMINED THAT ISOLATION VALVE LEAKAGE BETWEEN    |
| CCW TRAIN 'B' AND THE CCW NON-CRITICAL LOOP OBSERVED DURING A [TECHNICAL     |
| SPECIFICATION] SURVEILLANCE EXCEEDED ITS ACCEPTABLE LIMIT FOR OPERATION IN   |
| MODES 1 THROUGH 4, AND TRAIN B CCW COULD HAVE BEEN INOPERABLE PRIOR TO SHUT  |
| DOWN.  TESTS WERE PERFORMED TO ATTEMPT TO DETERMINE WHETHER THIS LEAKAGE     |
| EXISTED DURING OPERATION IN MODES 1 THROUGH 4 PRIOR TO PLANT SHUT DOWN.      |
| HOWEVER, THE TESTS WERE UNABLE TO DETERMINE THAT THE LEAKAGE DID NOT EXIST   |
| PRIOR TO SHUT DOWN.  DURING THE PAST CYCLE OF PLANT OPERATION, IF A SEISMIC  |
| EVENT WERE TO HAVE OCCURRED WHILE TRAIN 'A' WAS OUT OF SERVICE, THERE WAS A  |
| POTENTIAL FOR THE CCW TO FAIL TO MEET ITS REQUIRED 7 DAYS OF OPERATION       |
| WITHOUT MAKEUP.  THEREFORE, SCE IS CONSERVATIVELY MAKING THIS REPORT AS A    |
| NON-EMERGENCY 4-HOUR REPORT IN ACCORDANCE WITH 10CFR50.72(b)(2)(iii) - A     |
| CONDITION THAT ALONE COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY      |
| FUNCTION OF THE CCW.                                                         |
|                                                                              |
| "CCW IS PRESENTLY CAPABLE OF PERFORMING ITS SUPPORT FUNCTION FOR SHUTDOWN    |
| COOLING IN MODES 5 AND 6.  THE ISOLATION VALVES' ACTUATORS WERE              |
| DISCONNECTED, THE VALVES WERE MANUALLY SEATED.  THE MEASURED LEAKAGE WAS     |
| WELL BELOW THE ACCEPTABLE LEVEL FOR OPERATION IN MODES 1 THROUGH 4.  THE     |
| ACTUATORS WERE RE-CONNECTED TO PROVIDE FOR REMOTE OPERATION.  THE            |
| INVESTIGATION OF THE CAUSE AND CORRECTIVE ACTIONS IS ON-GOING.               |
|                                                                              |
| "UNIT 3 IS IN MODE 1 AND UNAFFECTED BY THIS CONDITION."                      |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35215       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 01/05/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 15:12[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        01/05/1999|
+------------------------------------------------+EVENT TIME:        13:40[CST]|
| NRC NOTIFIED BY:  TIM BORGEN                   |LAST UPDATE DATE:  01/05/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNU                   |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |CHRIS GRIMES, NRR    EO      |
|AAEC 50.72(a)(1)(i)      EMERGENCY DECLARED     |JOSEPH GIITTER, AEOD IRD     |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |JOHN HANNON, NRR     EO      |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |WAYNE STORE          FEMA    |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT, AUTOMATIC REACTOR TRIP, AND PARTIAL LOSS OF OFFSITE POWER DUE |
| TO AN EXPLOSION OF A STATION AUXILIARY TRANSFORMER                           |
|                                                                              |
| At 1311 CST, a Unit 1 automatic reactor trip occurred due to an explosion of |
| the '1M' station auxiliary transformer.  The licensee's fire brigade         |
| responded to the subsequent fire and extinguished the fire within several    |
| minutes.  The '1R' reserve transformer (which is located next to the '1M'    |
| transformer) was also lost possibly due to its proximity to the explosion.   |
| The loss of both the '1M' and 1R' transformers (which are located outside of |
| the main turbine building) caused the loss of non-safeguards buses 11, 12,   |
| 13, and 14.  This in turn caused the loss of all condensate and feedwater    |
| pumps, circulating water pumps, and reactor coolant pumps.  Auxiliary        |
| feedwater automatically initiated as required.  All Unit 1 safeguards buses  |
| remained energized from normal offsite power.  All rods fully inserted upon  |
| receipt of the reactor trip.  There were three first out indicators (low-low |
| steam generator pressure on the 11 steam generator, steam generator low-low  |
| level on the 12 steam generator, and high flux rate trip), and the exact     |
| causes of the reactor trip and transformer explosion are currently under     |
| investigation.  There were no emergency core cooling system actuations, and  |
| none were expected.  All systems functioned as required, and there were no   |
| personnel injuries.                                                          |
|                                                                              |
| Unit 1 is currently stable in Hot Shutdown.  Normal charging and letdown,    |
| auxiliary spray and one pressurizer heater, and natural circulation are      |
| being used to maintain primary system inventory, pressure, and transport     |
| control.  Auxiliary feedwater is supplying water to the steam generators,    |
| and secondary steam is being dumped to atmosphere.  There is no indication   |
| of steam generator tube leakage.  Efforts are currently underway to restore  |
| power to non-safeguards buses 13 and 14.                                     |
|                                                                              |
| Unit 2 was unaffected by this event.  It is currently operating at 60%       |
| reactor power following performance of an outage, and power ascension is in  |
| progress.                                                                    |
|                                                                              |
| At 1340 CST, the licensee declared a Notification of Unusual Event due to    |
| conditions warranting increased awareness by the plant operations staff.     |
| This was later revised to be conditions hazardous to plant operations (near  |
| or onsite explosion).  The licensee currently plans to terminate the Unusual |
| Event when one reactor coolant pump has been returned to service.            |
|                                                                              |
| The licensee notified the NRC resident inspector as well as the applicable   |
| state and local agencies.  The licensee may also issue a press release.      |
|                                                                              |
| ******************** UPDATE AT 1953 EST ON 01/05/99 FROM TIM BORGEN TO       |
| TROCINE ********************                                                 |
|                                                                              |
| The licensee terminated the Unusual Event at 1843 CST.  Unit 1 is currently  |
| in a stable condition meeting all technical specification requirements.      |
| Power has been restored to the 11, 12, 13, and 14, non-safeguards buses via  |
| back feed from the '2R' transformer.  The 12 reactor coolant pump was        |
| started at 1835 CST, and the licensee plans to start the 11 reactor coolant  |
| pump within a few minutes.  The circulating pumps were restored to service   |
| several hours ago, and the licensee plans to restore condensate pumps        |
| shortly.                                                                     |
|                                                                              |
| The licensee notified the NRC resident inspector and plans to notify the     |
| applicable state and local agencies.  The licensee may also issue a press    |
| release tomorrow.  The NRC Operations Officer notified the R3DO (Clayton),   |
| NRR EO (Hannon), AEOD IRD (Giitter), and FEMA (Ken Ciboch).                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35216       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 01/05/1999|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 15:12[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        01/05/1999|
+------------------------------------------------+EVENT TIME:        13:40[CST]|
| NRC NOTIFIED BY:  RANDY HASTINGS               |LAST UPDATE DATE:  01/06/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |CHRIS GRIMES, EO     NRR     |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |JOHN HANNON, EO      NRR     |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |JOSEPH GIITTER       IRD     |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| - UNIT 1 SHUTTING DOWN DUE TO INOPERABLE SI SYSTEM DUE TO FROZEN             |
| RECIRCULATION LINE -                                                         |
|                                                                              |
| UNIT 1 IS AT 100% POWER, AND UNIT 2 IS DEFUELED IN A REFUELING OUTAGE.       |
|                                                                              |
| A PORTION OF THE UNIT 1 SAFETY INJECTION PUMPS' RECIRCULATION LINE TO THE    |
| UNIT 1 REFUELING WATER STORAGE TANK APPEARS TO BE FROZEN DUE TO A LOSS OF    |
| HEAT TRACING DURING EXTREMELY COLD WEATHER.   THIS CONDITION RENDERS BOTH    |
| TRAINS OF THE UNIT 1 SAFETY INJECTION SYSTEM INOPERABLE.  THE UNIT 1         |
| CONTAINMENT SPRAY PUMPS USE THE SAME RECIRCULATION LINE AND ARE ALSO         |
| RENDERED INOPERABLE.  THE CONDITIONS OF TECHNICAL SPECIFICATION 15.3.0.B     |
| APPLY, AND THIS CONDITION APPEARS TO BE REPORTABLE AS A CONDITION THAT IS    |
| OUTSIDE THE PLANT DESIGN BASIS.                                              |
|                                                                              |
| THE ACTION STATEMENT FOR TECHNICAL SPECIFICATION 15.3.0.B REQUIRES THE       |
| LICENSEE TO INITIATE ACTION WITHIN 1 HOUR TO PLACE UNIT 1 IN HOT SHUTDOWN    |
| WITHIN 7 HOURS OF ENTERING THIS SPECIFICATION AND IN COLD SHUTDOWN WITHIN 37 |
| HOURS.                                                                       |
|                                                                              |
| THE LICENSEE IS CURRENTLY ATTEMPTING TO THAW THE LINE.                       |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
|                                                                              |
| ****************** UPDATE AT 1615 EST ON 01/05/98 FROM RANDY HASTINGS TO     |
| TROCINE ******************                                                   |
|                                                                              |
| The licensee initiated the technical specification required load reduction   |
| at 1506 CST on 01/05/99.                                                     |
|                                                                              |
| The licensee informed the NRC resident inspector.  The NRC operations        |
| officer notified the R3DO (Clayton), NRR EOs (Grimes and Hannon),and AEOD    |
| IRD (Giitter).                                                               |
|                                                                              |
| ****************** UPDATE AT 2132  EST ON 01/05/99 FROM JOHN CELL TO TROCINE |
| ******************                                                           |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Enforcement discretion was requested [at approximately 1625 CST] and        |
| granted [at approximately 1820 CST] by the NRC regarding the [Unit 1]        |
| shutdown required by the frozen [recirculation] line.  Unit 1 is presently   |
| at 23% reactor power.  Plans are to raise reactor power to 30% and hold.     |
|                                                                              |
| "Actions underway include [a] 50.59 evaluation of an alternate recirculation |
| path that will restore the operability of one [safety injection] pump.  An   |
| operability determination is being written to evaluate the operability of    |
| the [containment spray pumps] without the recirculation line.  These actions |
| are expected to be completed before the expiration of the enforcement        |
| discretion at 0140 CST [on 01/06/99]."                                       |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  The NRC Operations |
| Officer notified the R3DO (Clayton), NRR EO (Hannon), and AEOD IRD           |
| (Giitter).                                                                   |
|                                                                              |
| * * * UPDATE 0152 EST 1/6/98 FROM JOHN SELL TAKEN BY STRANSKY * * *          |
|                                                                              |
| "The original frozen line has been thawed and is being maintained warm by    |
| fluid circulation. An alternate SI pump recirculation path is currently      |
| being utilized which restores the Unit 1 'B' SI pump to operable. The use of |
| this path is supported by a 50.59 evaluation and an operability              |
| determination. The same operability determination restores both Unit 1 CSPs  |
| to operable status with minor compensatory measures.                         |
|                                                                              |
| "Unit 1 is being returned to 100% reactor power. The unit is in a 72-hour    |
| LCO until the normal SI recirculation path is restored, which will allow the |
| 'A' SI pump to be declared operable. This is anticipated later today after   |
| restoration procedures are approved and the SI recirc line heat tracing is   |
| restored."                                                                   |
|                                                                              |
| The NRC resident inspector will be informed of this update by the licensee.  |
| Notified R3DO (Clayton), EO (Hannon).                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35217       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS           REGION:  1  |NOTIFICATION DATE: 01/05/1999|
|    UNIT:  [1] [] []                 STATE:  MD |NOTIFICATION TIME: 15:17[EST]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        01/05/1999|
+------------------------------------------------+EVENT TIME:        15:12[EST]|
| NRC NOTIFIED BY:  TOM O'MEARA                  |LAST UPDATE DATE:  01/05/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM COOK         R1      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING A SMALL STEAM LEAK ON A MOISTURE SEPARATOR    |
| REHEATER DRAIN TANK                                                          |
|                                                                              |
| The licensee plans to notify the State Department of Labor Licensing and     |
| Regulation of a small steam leak on the 11 moisture separator reheater drain |
| tank, which is an ASME Section VIII pressure vessel.  There is no indication |
| of steam generator tube leakage, there is no effect on plant operations, and |
| there were no personnel injuries.  The area has been cordoned off as a       |
| precaution, but the licensee does not expect the tank to catastrophically    |
| fail.  There are two welds for the 1-inch pad on top of the tank that are    |
| still holding, and the licensee stated that the steam leak appears to be     |
| coming from an inside weld through a tell tail on the 1-inch pad.  The       |
| outside welds appear to be intact.                                           |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35218       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 01/05/1999|
|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 15:18[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        01/05/1999|
+------------------------------------------------+EVENT TIME:        13:56[EST]|
| NRC NOTIFIED BY:  JEFF MOSHER                  |LAST UPDATE DATE:  01/05/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LEN WERT             R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING INOPERABILITY OF THE SPILLWAY EMERGENCY       |
| DIESEL GENERATOR                                                             |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 1356 hours on 01/05/99, the Federal Emergency Regulatory Commission      |
| (FERC) was notified of the inoperability of the North Anna spillway          |
| emergency diesel generator in accordance with the requirements of            |
| 18CFR12.10(a).  The diesel generator failed its operability test due to the  |
| engine water temperature being below the acceptable range of 165 - 195F.    |
| Water temperature during the test was 155F.  A work request has been        |
| initiated to identify and correct the cause of this problem in a timely      |
| manner.  The diesel generator remains available."                            |
|                                                                              |
| The licensee stated that the spillway emergency diesel generator is not      |
| safety related and that the units are not in any limiting conditions for     |
| operation as a result of this issue.                                         |
|                                                                              |
| In addition to the FERC, the licensee notified the NRC resident inspector.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35219       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 01/05/1999|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 16:15[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        01/05/1999|
+------------------------------------------------+EVENT TIME:        16:13[EST]|
| NRC NOTIFIED BY:  BOB SMITH                    |LAST UPDATE DATE:  01/05/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM COOK         R1      |
|10 CFR SECTION:                                 |SUSAN SHANKMAN, EO   NMSS    |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |FEMA, DOE, USDA, HHS FAX     |
|                                                |EPA, DOT/NAT RES CTR FAX     |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| - Connecticut notified that 840 gallons of waste water containing trace      |
| amounts of tritium leaked into Niantic Bay -                                 |
|                                                                              |
| At 0200 on 01/04/99, a leak in a heater loop for the Unit 3 'A' waste test   |
| tank (WTT) was discovered.  Waste water in the WTT contained radioactivity   |
| and boric acid.  The leak  (approximately 1 - 2 gallons per minute) was      |
| isolated.  Initial indications were that this waste water was contained      |
| within the yard drain system.  Upon subsequent investigations, it was        |
| determined that, conservatively estimated, 840 gallons of liquid (4% of tank |
| volume) leaked from the WTT.  A berm surrounding the tank had been installed |
| due to a prior leak but did not contain this leak.  Sampling performed at    |
| discharge serial number DSN-006 taken after the event indicated the presence |
| of tritium.                                                                  |
|                                                                              |
| Based on the above, it is believed that waste water from this leak flowed to |
| a nearby yard drain and then discharged to Niantic Bay via DSN-006.  The     |
| waste water from this leak contained radioactivity which is not addressed in |
| the Millstone NPDES permit at DSN-006 nor are the WTTs listed as a source of |
| waste water for DSN-006.  Additionally, upon subsequent surveys of the storm |
| drain system, tritium was detected at the DSN-006 sample point.  As a        |
| result, this event was reported by the licensee to the Connecticut           |
| Department of Environmental Protection Spills Division and Permitting        |
| Division and local officials.                                                |
|                                                                              |
| The licensee plans to inform the NRC resident inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35220       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 01/05/1999|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 19:14[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        01/05/1999|
+------------------------------------------------+EVENT TIME:        15:18[EST]|
| NRC NOTIFIED BY:  FREDERICK SMITH              |LAST UPDATE DATE:  01/05/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       95       Power Operation  |95       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC START OF AN ANNULUS EXHAUST GAS TREATMENT SYSTEM FAN DURING TRAIN  |
| RESTORATION                                                                  |
|                                                                              |
| While returning annulus exhaust gas treatment system (AEGTS) train 'B' to    |
| standby readiness from secured status, the 'B' fan automatically started     |
| when the fan control switch was placed in the 'standby' position.  The       |
| licensee believes that the initiating signal may not have been valid and     |
| that the cause may have been a faulty flow switch.  Reportability is still   |
| under investigation.                                                         |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+