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Event Notification Report for June 28, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/27/2000 - 06/28/2000

                              ** EVENT NUMBERS **

37061  37087  37112  37117  37118  37119  37120  37121  37122  37123  37125 
37126  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37061       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 06/06/2000|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 12:47[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        06/06/2000|
+------------------------------------------------+EVENT TIME:        10:20[EDT]|
| NRC NOTIFIED BY:  DENNIS MAY                   |LAST UPDATE DATE:  06/27/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TOM MOSLAK           R1      |
|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                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE            |
|                                                                              |
| After completion of HPCI pump surveillance testing, a check for freedom of   |
| movement and proper reset action of the overspeed trip tappet was performed. |
| As a result of this check, an adjustment was found to be necessary for the   |
| turbine stop valve reset time.  Attempts to make this adjustment resulted in |
| inoperability of the reset function of the overspeed trip.  HPCI was         |
| declared inoperable and Technical Specification limiting condition for       |
| operation 3.5E(3) was entered.  HPCI will still start if called upon but if  |
| it trips on overspeed HPCI will become inoperable.                           |
|                                                                              |
| Reactor Core Isolation Cooling, Emergency Diesel Generators, and all other   |
| Emergency Core Cooling Systems are fully operable if needed.  The electrical |
| grid is stable.                                                              |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| * * * UPDATE 1252EDT ON 6/27/00 FROM DAVID HALLONQUIST TO S. SANDIN * * *    |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "This notification serves as retraction of a prior 10 CFR 50.72 notification |
| regarding High Pressure Coolant Injection (HPCI) operability. The original   |
| notification is NRC event report number 37061 and was reported on 6/6/00.    |
|                                                                              |
| "At that time, during routine surveillance testing, it was discovered that   |
| the HPCI over-speed trip did not reset without additional operator action.   |
| The event was reported because the cause for the failure to reset had not    |
| been determined and, therefore, it was not known whether the condition could |
| have challenged HPCI ability to perform its intended function.               |
|                                                                              |
| "Subsequent engineering review identified that the failure to automatically  |
| reset had been caused by inappropriate test methods. It was also determined  |
| that the over-speed trip reset concern would not have affected HPCI system   |
| ability to meet its design function for high pressure injection.             |
|                                                                              |
| "In addition, the HPCI over-speed reset is NOT a safety function of the VY   |
| safety system. As addressed in the VY licensing basis, the reset is required |
| if the HPCI system had already malfunctioned. The identified condition,      |
| therefore, would not have impacted system operability.                       |
|                                                                              |
| "Based on the above, the 50.72 notification is retracted."                   |
|                                                                              |
| The licensee will inform the NRC Resident Inspector.  Notified R1DO(Morris). |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37087       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 06/15/2000|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 21:54[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        06/15/2000|
+------------------------------------------------+EVENT TIME:        19:15[CDT]|
| NRC NOTIFIED BY:  MARSHALL FUNKHOUSER          |LAST UPDATE DATE:  06/27/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID HILLS          R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE CORE SPRAY (HPCS) DECLARED INOPERABLE DUE TO INCOMPLETE POST   |
| MODIFICATION TESTING OF IT'S ASSOCIATED DIESEL GENERATOR                     |
|                                                                              |
| "At 1915 on 6/15/00 a Engineering review of a plant modification to the      |
| Division 3 Diesel Generator (DG) determined that the Post Modification       |
| Testing did not verify proper operation of the Loss of Off-Site Power (LOOP) |
| circuitry. This modification had only been performed to Division 3 DG and    |
| therefore Division 1 and 2 DG's are not affected. Division 3 DG provides     |
| power to the High Pressure Core Spray (HPCS) pump. The failure of Division 3 |
| DG to operate during a LOOP would have prevented HPCS from operating. The    |
| loss of a single train safety system such as HPCS is reportable under        |
| 10CFR50.72(b)(2)(iii)(D)."                                                   |
|                                                                              |
| The plant modification involved rewiring the electrical circuit to correct   |
| for a degraded voltage condition and was completed on 1/24/99.  Post         |
| modification testing was completed on 1/31/99.  HPCS has been declared       |
| inoperable but is available, if needed, pending completion of additional     |
| testing.  The licensee will inform the NRC Resident Inspector.               |
|                                                                              |
| * * * UPDATE 2115EDT ON 6/27/00 FROM CHEAR TO S. SANDIN * * *                |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "Further review of this issue has determined that Division 3 Diesel          |
| Generator (DG) output breaker control circuit has been operable since        |
| installation of the modification and the plant was never in a condition that |
| alone could have prevented fulfillment of the safety function. Therefore,    |
| Clinton Power Station is retracting Event Notification # 37087."             |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  Notified R3DO(Leach).     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37112       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD                REGION:  3  |NOTIFICATION DATE: 06/25/2000|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 20:27[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/25/2000|
+------------------------------------------------+EVENT TIME:        17:45[CDT]|
| NRC NOTIFIED BY:  BURKETT                      |LAST UPDATE DATE:  06/27/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHAEL JORDAN       R3      |
|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                                   
+------------------------------------------------------------------------------+
| PLANT MADE NOTIFICATION TO THE NATIONAL RESPONSE CENTER AND THE ILLINOIS     |
| EMERGENCY MANAGEMENT AGENCY OF AN OIL SPILL.                                 |
|                                                                              |
| These notifications were made due to a small quantity of oil in the runoff   |
| ditch.  The quantity of oil is estimated to be 5 gallons and was due to an   |
| overflow of their lube oil separator.  Cleanup efforts are in progress.      |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
|                                                                              |
| * * * UPDATE ON 6/27/00 AT 1240 EDT BY CAL WALRATH TO FANGIE JONES * * *     |
|                                                                              |
| The licensee made a press release and notified the NRC Resident Inspector    |
| and the state and local authorities of the press release.                    |
|                                                                              |
| The operations officer notified the R3DO (Melvyn Leach).                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37117       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 06/26/2000|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 19:23[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        06/26/2000|
+------------------------------------------------+EVENT TIME:        18:53[EDT]|
| NRC NOTIFIED BY:  RICK O'CONNOR                |LAST UPDATE DATE:  06/27/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |SCOTT MORRIS         R1      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT MANUALLY TRIPPED FOLLOWING A LOSS OF THE "A" MAIN FEEDWATER PUMP (MFP)  |
|                                                                              |
| AT 1900EDT ON 6/26/00, THE UNIT EXPERIENCED A PLANT SETBACK TO 55% POWER     |
| FOLLOWING THE LOSS OF THE "A" MFP.  OPERATORS INSERTED A MANUAL REACTOR TRIP |
| AS STEAM GENERATOR LEVELS APPROACHED THE LOW LEVEL TRIP SETPOINT.  ALL       |
| SYSTEMS FUNCTIONED AS REQUIRED WITH  ALL CONTROL RODS FULLY INSERTING.       |
| EMERGENCY FEEDWATER (EFW) ACTUATED AS EXPECTED.  THE MAIN CONDENSER IS       |
| AVAILABLE ACCEPTING DECAY HEAT VIA STEAM BYPASS.  NO PRIMARY/SECONDARY       |
| SAFETIES/RELIEFS LIFTED DURING THE TRANSIENT.  ALL THREE OFFSITE POWER       |
| SOURCES ARE AVAILABLE.                                                       |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND WILL ISSUE A PRESS      |
| RELEASE.                                                                     |
|                                                                              |
| ********** UPDATE AT 0015 ON 06/27/00 FROM DAMON RITTER TO LEIGH TROCINE     |
| **********                                                                   |
|                                                                              |
| The licensee updated this event notification to document an abnormal         |
| post-trip response and to correct the event time.  The following text is a   |
| portion of a facsimile received from the licensee:                           |
|                                                                              |
| "Subsequent to the trip, one channel of intermediate and source range        |
| nuclear instrumentation did not energize.  The cause is under investigation. |
| [The licensee stated that this did not place the unit in a limiting          |
| condition for operation because there was still one channel in operation.]   |
| Additionally, the event time for the event notification is corrected.  The   |
| reactor trip was initiated at 1853 [on] 26 June 2000 [in lieu of 1900]."     |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  The NRC operations |
| officer notified the R1DO (Morris).                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37118       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 06/26/2000|
|    UNIT:  [1] [2] []                STATE:  NJ |NOTIFICATION TIME: 22:17[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        06/26/2000|
+------------------------------------------------+EVENT TIME:        20:58[EDT]|
| NRC NOTIFIED BY:  S. SAUER                     |LAST UPDATE DATE:  06/27/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |SCOTT MORRIS         R1      |
|10 CFR SECTION:                                 |                             |
|AESS 50.72(b)(1)(v)      EMERGENCY SIREN INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       92       Power Operation  |92       Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF A SIGNIFICANT PORTION OF OFFSITE EMERGENCY SIRENS                    |
|                                                                              |
| "NOTIFIED BY EMERGENCY PLANNING PERSONNEL THAT AS OF 2058[EDT] ON 6/26/00,   |
| NINETEEN [19] OFFSITE SIRENS HAD BEEN LOST.  AS OF 2158[EDT] EFFORTS TO      |
| RESTORE ARE STILL IN PROGRESS.  OF THE NINETEEN [19], SIXTEEN [16] ARE IN    |
| DELAWARE AND THREE [3] ARE IN NEW JERSEY.  THE NINETEEN [19] SIRENS          |
| REPRESENTS LOSS OF GREATER THAN 25% OF THE TOTAL OF SEVENTY-ONE [71]         |
| SIRENS."                                                                     |
|                                                                              |
| THE LICENSEE COULD NOT IDENTIFY THE CAUSE, HOWEVER, THEY ARE CURRENTLY       |
| EXPERIENCING ADVERSE WEATHER.  THIS REPORT ALSO AFFECTS THE HOPE CREEK       |
| STATION.  THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.               |
|                                                                              |
| ********** UPDATE AT 0043 ON 06/27/00 FROM STEVE SAUER TO LEIGH TROCINE      |
| **********                                                                   |
|                                                                              |
| At 2340 on 06/26/00, the licensee was notified that the bulk of the offsite  |
| emergency sirens (all but three) had been restored to service.               |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  The NRC operations |
| officer notified the R1DO (Morris).                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37119       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 06/27/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 01:14[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        06/26/2000|
+------------------------------------------------+EVENT TIME:        23:22[EDT]|
| NRC NOTIFIED BY:  MARK ABRAMSKI                |LAST UPDATE DATE:  06/27/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |SCOTT MORRIS         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          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) ACTUATIONS DUE TO THE TRIPPING   |
| OF ELECTRICAL PROTECTION ASSEMBLIES (EPA) AND SUBSEQUENT HALF SCRAM          |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[The unit experienced a loss] of [the] 'A' [reactor protection system       |
| (RPS)] bus[.  Output] EPAs tripped causing [this 120-volt AC] bus to         |
| de-energize.  This caused the reactor building ventilation to isolate[,]     |
| both [standby gas treatment systems (SBGT)] to start[, and the] 'A'          |
| [hydrogen/oxygen (H2/O2)] monitor to trip (PCIS valves).  [The reactor water |
| cleanup (RWCU)] system tripped on low flow due to 12MOV-15 closure (PCIS     |
| valve)."                                                                     |
|                                                                              |
| The licensee stated that there was nothing unusual or not understood and     |
| that all systems functioned as required.  The licensee also stated that the  |
| cause of this event is currently under investigation.  The EPAs tripped      |
| under normal supply, and the RPS motor-generator set was functioning         |
| properly.  There were no maintenance or surveillance activities underway at  |
| the time of the event.                                                       |
|                                                                              |
| The reactor building and H2/O2 analyzers have since been un-isolated.  SBGT  |
| is currently under normal operation and is being used for venting.  RWCU has |
| not yet been restored to normal.                                             |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37120       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 06/27/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 08:36[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/26/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        12:40[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/27/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MELVYN LEACH         R3      |
|  DOCKET:  0707002                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JEFF CASTLE                  |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 RESPONSE (24-HOUR REPORT)                                 |
|                                                                              |
| The following text is a portion of a facsimile received from Portsmouth      |
| personnel:                                                                   |
|                                                                              |
| "At 1240 hours on 06/26/00, it was discovered that a Nuclear Criticality     |
| Safety Approval (NCSA) requirement had not been met during sampling and      |
| batching operations in the X-710 building.  The contents of four polybottles |
| were batched into two five-gallon containers without adequate documentation  |
| showing that the sampling data was for Nuclear Criticality Safety purposes.  |
| A review of the sample results indicated that all the results did not meet   |
| the NCSA requirements for independent measurements.  This violated           |
| NCSA-PLANT053.A03 requirement #13 which states, 'The results of sample       |
| analysis or NDA (Non-Destructive Assay) measurements shall not be used for   |
| NCS purposes if the documentation does not show that the results were        |
| determined as NCS significant results.'  (Basis:  The measurements and       |
| analysis must be performed to independent criteria to be acceptable for NCS  |
| purposes.)"                                                                  |
|                                                                              |
| "Two independent measurements of mass of the batching material are required  |
| to ensure double contingency.  Only one independent measurement of mass was  |
| available.  The other measurement did not meet independent criteria per NCSA |
| requirements.  The absence of a second independent measurement constituted a |
| loss of one control of the double contingency principle."                    |
|                                                                              |
| "A second independent measurement was performed, and compliance was          |
| reestablished with NCSA-PLANT053.A03 at 1557 hours on 06/26/00."             |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:  The safety significance of this event is    |
| very low.  The total U235 involved in each of the two batches [is] 0.2154    |
| grams and 2.1868 grams, respectively.  To re-establish NCS compliance,       |
| repeat NCS measurements for each batch were performed to confirm that the    |
| total mass meets the requirements of NCSA-PLANT013, Batching Solutions and   |
| Solids."                                                                     |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW           |
| CRITICALITY COULD OCCUR):  Prior to batching the contents in accordance with |
| NCSA-PLANT013, documentation of analysis results are checked to ensure that  |
| the measurements were handled as 'NCS Significant' and independently         |
| analyzed in accordance with NCSA-PLANT053.  Without independent results, a   |
| single measurement error could result in more than a safe mass being batched |
| into a container.  If this mass were then subject to the correct geometry,   |
| moderation, and reflection conditions, a criticality could occur."           |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):    |
| Mass is the only controlled parameter.  Two independent measurements of mass |
| are required to ensure double contingency.  Since independence of NDA mass   |
| measurements is called into question, only one independent estimate of mass  |
| is available.  The absence of a second independent NDA mass measurement      |
| represents a loss of one double contingency control."                        |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS    |
| LIMIT AND % WORST CASE OF CRITICAL MASS):  The total U235 involved in each   |
| of the two batches [is] 0.2154 grams and 2.1865 grams, respectively.         |
| Uranium mass is measured in batching operations to ensure the U235 mass in   |
| the final container is less than 350 grams U235 which is less than half the  |
| minimum critical mass at 100% enrichment and optimum moderation, geometry,   |
| and reflection conditions."                                                  |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES:  Nuclear criticality safety controls        |
| include independent mass measurements of U235.  Failure to ensure that NCS   |
| significant measurements were used lead to a potential failure of the        |
| measurements."                                                               |
|                                                                              |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:  |
| A second independent NDA measurement was performed to verity total mass of   |
| U235 (<1 gram per bucket/container).  Compliance with NCSA-Plant053.A03 was  |
| re-established at 1557 hours based on the results of the NDA measurements."  |
|                                                                              |
| Portsmouth personnel notified the NRC resident inspector and the site        |
| Department of Energy manager.                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37121       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2                    REGION:  4  |NOTIFICATION DATE: 06/27/2000|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 11:57[EDT]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        06/27/2000|
+------------------------------------------------+EVENT TIME:        05:30[PDT]|
| NRC NOTIFIED BY:  DAVE SWANK                   |LAST UPDATE DATE:  06/27/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MAIN STEAM ISOLATION VALVES (MSIVs) ISOLATED DUE TO SPURIOUS GROUP 1         |
| ISOLATION SIGNAL                                                             |
|                                                                              |
| "This event is being reported per 10CFR50.72(b)(2)(ii).                      |
|                                                                              |
| "At 0530 hours the MSIVs inadvertently isolated due to a spurious group 1    |
| primary containment isolation valve logic (NS4) signal.                      |
|                                                                              |
| "In support of required surveillance testing of RPS EPA breakers, RPS 'B'    |
| bus had been transferred to normal from its alternate power supply. NS4 'B'  |
| isolation logic was inadvertently not reset as part of the restoration       |
| following this power supply transfer. When bus RPS 'A' was de-energized as   |
| part of the planned transfer to the alternate power supply it caused the NS4 |
| 'A' isolation logic relays to de-energize and resulted in a closure signal   |
| to all MSIVs. All eight MSIVs closed as expected.                            |
|                                                                              |
| "The plant was in Mode 4 at approximately 180F at the time of the event.    |
| Shutdown cooling had been removed from service in preparation for the power  |
| supply transfer. Following reset of the NS4 isolation logic. shutdown        |
| cooling was restored with the reactor coolant temperature at approximately   |
| 187F. The MSIVs may be re-opened as needed,"                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37122       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 06/27/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 12:04[EDT]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        06/27/2000|
+------------------------------------------------+EVENT TIME:        09:30[EDT]|
| NRC NOTIFIED BY:  FRANK CIGANIK                |LAST UPDATE DATE:  06/27/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |SCOTT MORRIS         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  |85       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NEW JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION (NJ DEP) NOTIFIED OF       |
| EFFLUENT DISCHARGE TEMPERATURE VIOLATION                                     |
|                                                                              |
| ON 6/26/00 AT 1844EDT AND 1859EDT, EFFLUENT DISCHARGE TEMPERATURE WAS        |
| MEASURED AT 106.62 AND 106.60 DEGREES F.  THIS EXCEEDS THE LIMIT OF 106 +0.5 |
| DEGREES F WHICH REQUIRES NOTIFICATION TO NJ DEP.  CORRECTIVE ACTION TAKEN    |
| INCLUDED LOWERING POWER TO REDUCE EFFLUENT TEMPERATURE.  THE LICENSEE ALSO   |
| INTENDS TO CHECK THE ALARM SETPOINTS.                                        |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37123       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 06/27/2000|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 14:17[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        06/27/2000|
+------------------------------------------------+EVENT TIME:        14:00[EDT]|
| NRC NOTIFIED BY:  DENNIS BEMIS                 |LAST UPDATE DATE:  06/27/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |SCOTT MORRIS         R1      |
|10 CFR SECTION:                                 |                             |
|AESS 50.72(b)(1)(v)      EMERGENCY SIREN INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| EMERGENCY SIRENS INOPERABLE DUE TO PLANNED MAINTENANCE                       |
|                                                                              |
| "PLANNED LOSS OF POWER TO THE NEWINGTON SIREN ACTIVATION CONTROL REPEATER    |
| FOR GREATER THAN 1 HOUR.  POWER SHOULD BE RESTORED WITHIN 1-2 HOURS.  THE    |
| EOF LOST CAPABILITY TO ALL 94 SIRENS TO BE ACTIVATED.  EACH LOCAL COMMUNITY  |
| STILL HAD THE ABILITY TO ACTIVATE THEIR RESPECTIVE SIRENS."                  |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37125       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2                    REGION:  4  |NOTIFICATION DATE: 06/27/2000|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 20:35[EDT]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        06/27/2000|
+------------------------------------------------+EVENT TIME:        15:29[PDT]|
| NRC NOTIFIED BY:  OJ BROOKS                    |LAST UPDATE DATE:  06/27/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GAIL GOOD            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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MAIN STEAM ISOLATION VALVES CLOSED                                           |
|                                                                              |
| "The Main Steam Isolation Valves closed due to Low Vacuum closure isolation  |
| signal. The low vacuum isolation logic had not been completely bypassed as   |
| required by PPM 3.2.1, prior to breaking main condenser vacuum.              |
|                                                                              |
| "The RPV is in Shutdown Cooling at 137F cooling down to a band of 100 to    |
| 120F. Shutdown cooling was not impacted by the isolation."                  |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37126       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 06/27/2000|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 22:00[EDT]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        06/27/2000|
+------------------------------------------------+EVENT TIME:        21:25[EDT]|
| NRC NOTIFIED BY:  DOUG SCHROEDER               |LAST UPDATE DATE:  06/27/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CAUDLE JULIAN        R2      |
|10 CFR SECTION:                                 |                             |
|AESS 50.72(b)(1)(v)      EMERGENCY SIREN INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| LOSS OF EMERGENCY SIRENS DUE TO ADVERSE WEATHER                              |
|                                                                              |
| "At 2125 Notified by Emergency Preparedness that Chatam County lost all      |
| Siren Capability for a period of 8 minutes due to a lightning strike. Siren  |
| capability has been restored."                                               |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+