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Event Notification Report for February 22, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/19/1999 - 02/22/1999

                              ** EVENT NUMBERS **

35359  35378  35384  35385  35386  35387  35388  35389  35390  35391  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35359       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 02/09/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 18:37[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        02/09/1999|
+------------------------------------------------+EVENT TIME:        18:20[EST]|
| NRC NOTIFIED BY:  JEFF SHIPE                   |LAST UPDATE DATE:  02/19/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAURIE PELUSO        R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - Non-conservative dose calculation methodology is a condition outside the   |
| design basis of Unit 1 -                                                     |
|                                                                              |
| As a result of LER 2-97-008 corrective actions, non-conservative inputs have |
| been identified that is associated with the Beaver Valley Power Station      |
| (BVPS) methodology in calculating radiation doses for accidents which must   |
| analyze for a concurrent iodine spike as part of their radiological          |
| analyses.  The identified non-conservative factors during past operation,    |
| could have resulted in the calculated control room personnel dose values     |
| exceeding 10CFR50 Appendix A, Criterion 19 thyroid limits.  Since BVPS no    |
| longer has reasonable assurance that acceptance criteria for control room    |
| personnel dose limits per Criterion 19 would have been met during past       |
| operation, the identified non-conservative dose calculation methodology was  |
| a condition which was outside the design basis of the plant per              |
| 10CFR50.72(b)(1)(ii).  This condition is also being evaluated for the        |
| criteria in 10CFR Part 21.                                                   |
|                                                                              |
| For BVPS, the only Design Basis Accidents (DBAs) which involve a concurrent  |
| iodine spike analysis are Main Steam Line Break, Small Line Breaks (e.g.,    |
| letdown line break outside containment), and Steam Generator Tube Rupture.   |
| The most significant of the non-conservative issues is purification (i.e.,   |
| letdown) flow, which was given as 60 gpm.  This is the lower limit of the    |
| plant design flow rate range of 60-120 gpm.  Analysis using 60 gpm results   |
| in a significant underestimation of the concurrent iodine spike source term  |
| as compared to operation at the upper design limit of 120 gpm.  Of lesser    |
| importance were underestimated demineralizer decontamination factor,         |
| overestimated reactor coolant system (RCS) mass and inadequate use of RCS    |
| leakage as an iodine removal mechanism.  It has been determined that         |
| correcting the above identified non-conservative factor would raise          |
| calculated control room personnel dose values of those events analyzed for   |
| concurrent iodine spikes by at least 40% and potentially as high as 140%.    |
|                                                                              |
| Until the BVPS dose calculations can be formally revised to address the      |
| identified non-conservative factors, the station has placed administrative   |
| controls on the extent of steady state letdown flow to ensure that plant     |
| operation remains within past analyzed limits.  The influence of the other   |
| identified non-conservative factors have also been reviewed and determined   |
| not to be an operability concern at this time.                               |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.                     |
|                                                                              |
| * * * UPDATE AT 1110 ON 02/19/99 FROM JIM DAUGHERTY TO JOLLIFFE * * *        |
|                                                                              |
| The licensee is evaluating the above described issue and at 1600 on          |
| 02/18/99, they determined that it also meets the reportability criteria      |
| pursuant to l0CFR Part 21 specifically for Beaver Valley Unit 1. The generic |
| issue (Westinghouse issue) is applicable to both Beaver Valley Units I and   |
| 2.  A written report will be supplied pursuant to 10CFR Part 21 and          |
| I0CFR50.73 in a supplement to LER 2-97-008.                                  |
|                                                                              |
| Until the Beaver Valley dose calculations can be formally revised to address |
| the identified non-conservative factors, BVPS has implemented administrative |
| controls to ensure that plant operation remains within past analyzed         |
| limits.                                                                      |
|                                                                              |
| The licensee is continuing to evaluate this issue.                           |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.                     |
|                                                                              |
| The NRC Operations Officer notified the R1DO Jim Trapp and NRR Vern Hodge.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35378       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS                   REGION:  2  |NOTIFICATION DATE: 02/17/1999|
|    UNIT:  [1] [] []                 STATE:  NC |NOTIFICATION TIME: 13:05[EST]|
|   RXTYPE: [1] W-3-LP                           |EVENT DATE:        02/17/1999|
+------------------------------------------------+EVENT TIME:        12:19[EST]|
| NRC NOTIFIED BY:  MARK PALMER                  |LAST UPDATE DATE:  02/19/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANN BOLAND           R2      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|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  |7        Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED PLANT SHUTDOWN DUE TO FAILURE OF THE 'A'    |
| REACTOR TRIP BREAKER TO CLOSE RELIABLY DURING TESTING                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During [technical specification] surveillance testing [with the unit] at    |
| 100% power, a testing failure occurred on the train 'A' reactor trip         |
| breaker.  The test in progress was MST-I001, Train 'A' Solid State           |
| Protection System Actuation Logic and Master Relay Test.  During this test,  |
| the 'A' reactor trip breaker failed to close with the test pushbutton.  The  |
| following timeline occurred:"                                                |
|                                                                              |
| "0821- [The] train 'A' reactor trip bypass breaker [was racked in and        |
| closed].  This began a 2-hour time                                           |
| limit allowed for surveillance testing.                                      |
| 0916 - Reactor trip breaker 'A' failed to close with the test pushbutton.    |
| At this point, the 2-hour limit for                                          |
| surveillance testing ended, and [Technical Specification] 3.3.1, action 8,   |
| was entered.  This action                                                    |
| required the plant to be in Mode 3 within 6 hours.  The time to enter Mode 3 |
| is 1516.                                                                     |
| 1026 - NRC Region II representative, George MacDonald, [was] notified of     |
| [limiting condition for operation]                                           |
| and necessity to be in Mode 3 by 1516.  Mr. MacDonald was notified because   |
| [the] Harris resident                                                        |
| inspectors are out of town.                                                  |
| 1219 - [A generator] load reduction for plant shutdown [was commenced].      |
| Maintenance and engineering                                                  |
| personnel are investigating the problem."                                    |
|                                                                              |
| The licensee emphasized that the train 'A' reactor trip breaker did not fail |
| to open, which is its safety function.  The breaker only failed to re-close. |
| It has since been opened and re-closed several times during ongoing          |
| troubleshooting activities.  The licensee currently believes that the        |
| failure of the breaker to re-close reliably may be the result of a possible  |
| problem with the test circuitry allowing the test signal to stay in.         |
|                                                                              |
| Although all of the emergency diesel generators and emergency core cooling   |
| systems are operable and available if needed, the licensee stated that the   |
| emergency response data system is not available due to a Y2K problem.  (The  |
| Y2K problem is not related to the breaker problem.)                          |
|                                                                              |
|                                                                              |
| *** UPDATE ON 2/19/99 @ 1356 BY FLEMING TO GOULD ***                         |
|                                                                              |
| THE PLANT EXITED TS 3.3.1 ACTION 8 AT 1452 ON 2/17/99 WHILE AT 7% POWER.     |
| THE UNIT DID NOT DROP FROM THE GRID OR ENTER MODE 3 PRIOR TO DECLARING THE   |
| "A" REACTOR TRIP BREAKER OPERABLE AND IN-SERVICE WITH ITS BYPASS BREAKER     |
| OPEN.  AFTER EXITING THE LCO, POWER LEVEL WAS INCREASED AND THE REACTOR IS   |
| CURRENTLY AT 100% POWER.                                                     |
|                                                                              |
| THE ORIGINAL REPORT STATED THAT "ERDS NOT AVAILABLE DUE TO Y2K PROBLEM."  A  |
| SUBSEQUENT INVESTIGATION HAS REVEALED THAT ERDS REMAINED AVAILABLE           |
| IMMEDIATELY PRIOR TO AND DURING THE REPORTED EVENT. CONTROL ROOM STAFF WAS   |
| UNDER A MISTAKEN IMPRESSION THAT THE ERDS LINK WAS UNAVAILABLE DUE TO Y2K    |
| TESTING BY THE NRC.  A SERIES OF INCOMPLETE COMMUNICATIONS LED THEM TO THAT  |
| CONCLUSION.                                                                  |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
|                                                                              |
| REG2 RDO(BOLAND) WAS INFORMED.                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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:  02/19/1999|
|  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.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35385       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  COGEMA MINING INC.                   |NOTIFICATION DATE: 02/19/1999|
|LICENSEE:  COGEMA MINING INC.                   |NOTIFICATION TIME: 17:07[EST]|
|    CITY:  LINCH                    REGION:  4  |EVENT DATE:        02/17/1999|
|  COUNTY:  CAMPBELL                  STATE:  WY |EVENT TIME:        12:00[MST]|
|LICENSE#:  SUA-1341              AGREEMENT:  N  |LAST UPDATE DATE:  02/19/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LAWRENCE YANDELL     R4      |
|                                                |CHARLEY HAUGHNEY     NMSS    |
+------------------------------------------------+JOE HOLONICH         NMSS    |
| NRC NOTIFIED BY:  VASELIN (RSO)                |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MONITOR WELL PLACED ON EXCURSION STATUS                                      |
|                                                                              |
| A ROUTINE BI-WEEKLY WATER SAMPLE COLLECTED ON 02/17/99 FROM MONITOR WELL     |
| "6MW40", EXCEEDED ALL 3 OF ITS UPPER CONTROL LIMITS UCLs.  A CONFIRMATION    |
| SAMPLE WAS COLLECTED 2/19/99, WHICH ALSO EXCEEDED ALL 3 UCLs.  MONITOR WELL  |
| "6MW40" WAS THEN PLACED ON EXCURSION STATUS AS PER LICENSE SECTION 11.2 AND  |
| ITS SAMPLING FREQUENCY INCREASED TO WEEKLY.  "6MW40" IS A PERIMETER ORE ZONE |
| MONITOR WELL LOCATED APPROXIMATELY 180 FEET (MAX. CAN BE 300 FT) EAST OF THE |
| MINE UNIT 6 BOUNDARY AT THE CHRISTENSEN MINE, CAMPBELL COUNTY, WYOMING.  THE |
| NEAREST COMMUNITY IS LINCH, WYOMING, APPROXIMATELY 15 MILES TO THE           |
| SOUTHEAST.                                                                   |
|                                                                              |
|                                                                              |
| ANALYSIS DATA:                                                               |
|                                                                              |
| DATE            CHLORIDE mg/l    CONDUCTIVITY µmhos/cm²       ALKALINITY     |
| mg/l    URANIUM mg/l U3O8                                                    |
| SAMPLED           UCL  20.0                           UCL 1576               |
| UCL  95.2                   NO UCL                                           |
| ---------------------------------------------------------------------------- |
| ------------------------------------------------------------------------     |
| 2/17/99                         39.2                                    1861 |
| 386.2                        <0.4                                            |
|                                                                              |
| 2/19/99                         25.9                                    1660 |
| 260.8                        <0.4                                            |
|                                                                              |
| THERE ARE NO HEALTH OR ENVIRONMENTAL HAZARDS FROM THE RESULTS OF THIS        |
| EXCURSION.                                                                   |
|                                                                              |
| CORRECTIVE ACTION: OVER-RECOVERY PUMPING OF 50 GPM HAS BEGUN IN THE          |
| WELLFIELD AREA NEAREST MONITOR WELL "6MW40".                                 |
|                                                                              |
| A WRITTEN NOTIFICATION WILL BE SUBMITTED TO NRC URANIUM RECOVERY BRANCH      |
| WITHIN 7 DAYS.                                                               |
|                                                                              |
| HOO NOTE: SEE EVENT #35190                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35386       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 02/20/1999|
|    UNIT:  [] [] [3]                 STATE:  IL |NOTIFICATION TIME: 06:02[EST]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        02/20/1999|
+------------------------------------------------+EVENT TIME:        04:14[CST]|
| NRC NOTIFIED BY:  SALGADO                      |LAST UPDATE DATE:  02/20/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE JORDAN          R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     A          N       0        Cold Shutdown    |0        Cold Shutdown    |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| A FULL REACTOR SCRAM OCCURRED DURING RESTORATION LINEUP AFTER A  HYDROSTATIC |
| TEST                                                                         |
|                                                                              |
| Unit 3 experienced a full reactor scram (no rod motion), group 2 (Reactor    |
| Water Cleanup,  drywell atmosphere) isolation and group 3 (shutdown cooling) |
| isolation while in mode 4 (cold shutdown).  Actual reactor vessel water      |
| level was plus 32 inches (scram/isolation setpoint is approximately plus 15  |
| inches).  This event occurred during the restoration from the hydrostatic    |
| test lineup (probably a pressure spike on a instrument line during the       |
| restoration lineup caused this event).   Shutdown cooling was lost for       |
| approximately 10 minutes. There was no discernable rise in reactor vessel    |
| water temperature during the time period shutdown cooling was inoperable.    |
| The licensee is investigating the cause of the reactor scram and the group   |
| isolations.                                                                  |
|                                                                              |
| The NRC resident inspector will be informed of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35387       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 02/20/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 08:44[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/19/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        10:05[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  02/20/1999|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |MIKE JORDAN          R3      |
|  DOCKET:  0707001                              |CHARLEY HAUGHNEY     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  K. A. BEASLEY                |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| WATER INVENTORY CONTROL SYSTEM ACTIVATION                                    |
|                                                                              |
| A water inventory control system (WICS) activation occurred on C-360         |
| position 4 autoclave on February 19, 1999 at 1005 CST.  A high level drain   |
| primary alarm was received during a cylinder sampling heat cycle.  The       |
| safety system did operate as required (shuts off steam to the autoclave      |
| which reduces the amount of condensation in the autoclave).  The purpose of  |
| the WICS is to limit the amount of condensate in the autoclave. The cause of |
| this actuation is being investigated.  The certificate holder thinks that    |
| this event might have been caused by an invalid signal  and if it is         |
| determined that this event was caused by an invalid signal this event        |
| notification will be retracted at a later time.                              |
|                                                                              |
| The safety system actuation is reportable per Safety Analysis Report,        |
| section 6.9 Table 1, criteria J.2, Safety System actuation due to a valid    |
| signal as a 24-hour event notification.                                      |
|                                                                              |
|                                                                              |
| The NRC resident inspector was notified of this event.                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35388       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 02/20/1999|
|    UNIT:  [1] [2] [3]               STATE:  AZ |NOTIFICATION TIME: 10:30[EST]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        02/20/1999|
+------------------------------------------------+EVENT TIME:        06:48[MST]|
| NRC NOTIFIED BY:  DANN R. DAILEY               |LAST UPDATE DATE:  02/22/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE YANDELL     R4      |
|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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE OFFSITE EMERGENCY SIREN SYSTEM SILENT AND BACKUP TEST FAILED.            |
|                                                                              |
| On 02/20/99 at approximately 0648 MST, Palo Verde was notified by the        |
| Maricopa County Sheriff's Office (MCSO) of a failure of the Offsite Siren    |
| System in the Emergency Planning Zone.  The discovery was during a scheduled |
| silent test of the sirens by MCSO personnel.  At approximately 0720 MST, the |
| Department of Public Safety performed a back-up test of the Offsite Siren    |
| System that also failed.  Emergency Planning personnel have been notified    |
| and are responding to correct the problem.  Investigation of the above       |
| problem is in progress.                                                      |
|                                                                              |
| The NRC resident inspector was notified of this event by the licensee.       |
|                                                                              |
|                                                                              |
| ***Update by Dann R. Dailey on 02/20/99 at 1034 EST taken by MacKinnon***    |
|                                                                              |
| The Offsite Siren System was successfully tested and returned to service at  |
| 0820 MST. R4DO (Larry Yandell) notified.                                     |
|                                                                              |
| The NRC resident inspector will be notified of this update by the licensee.  |
|                                                                              |
|                                                                              |
| **** UPDATE ON 2/20/99 @ 1428 BY MARKS TO GOULD ***                          |
|                                                                              |
| ALL 39 SIRENS WERE RETURNED TO SERVICE AT 0820 MST.  CAUSE OF FAILURE WAS    |
| DUE TO PERSONNEL ERROR.  A TEST TONE WAS INADVERTENTLY LEFT ON THE PHONE     |
| LINE AND IT INTERFERED WITH THE ABILITY TO ACTIVATE THE OFF-SITE SIRENS.     |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.  THE REG 4 RDO(YANDELL) WAS INFORMED.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35389       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 02/20/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 21:38[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/19/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        23:00[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  02/20/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MIKE JORDAN          R3      |
|  DOCKET:  0707002                              |CHARLEY HAUGHNEY     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SPAETH                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CRITICALITY ACCIDENT ALARM SYSTEM (CAAS) "SLAVE" SYSTEM DECLARED             |
| INOPERABLE.                                                                  |
|                                                                              |
| AT 2300 ON 2/19/99, AN INSTRUMENT MAINTENANCE WORK CREW DISCOVERED THE       |
| NITROGEN BOTTLE VALVED OFF WHILE RESPONDING TO A TROUBLESHOOT AND REPAIR     |
| WORK PACKAGE FOR THE X-700 CAAS "SLAVE" SYSTEM.    THE REQUIRED ACTIONS FOR  |
| THIS LCO WERE NOT IMPLEMENTED UNTIL THE CAAS "SLAVE" SYSTEM WAS DECLARED     |
| INOPERABLE AT 2234                                                           |
|                                                                              |
| THIS DISCOVERY RESULTED IN A NONCOMPLIANCE WITH TECHNICAL SAFETY REQUIREMENT |
| (TSR) 2.8.3.1b LIMITING CONDITION OF OPERATION (LCO), WHICH STATES THE       |
| CRITICALITY ACCIDENT ALARM SHALL BE OPERABLE (AUDIBLE).                      |
|                                                                              |
| THE X-700 BUILDING IS PROVIDED WITH BOTH A CAAS CLUSTER WITH ITS ASSOCIATED  |
| NITROGEN BOTTLE AND A "SLAVE" NITROGEN-DRIVEN HORN SYSTEM (INCLUDES 3 HORNS) |
| TO PROVIDE ADEQUATE AUDIBILITY WITHIN THE BUILDING IN THE UNLIKELY EVENT OF  |
| A NUCLEAR CRITICALITY.                                                       |
|                                                                              |
| THE CAAS CLUSTER AND ITS ASSOCIATED NITROGEN HORN REMAINED OPERABLE          |
| THROUGHOUT THIS EVENT, THEREFORE, TSR COMPLIANCE WITH THE LCO.  CRITICALITY  |
| ACCIDENT DETECTION WAS MAINTAINED.                                           |
|                                                                              |
| THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR                       |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT.   |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS INFORMED AND THE DOE REPRESENTATIVE WILL BE   |
| NOTIFIED                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35390       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 02/21/1999|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 11:28[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        02/20/1999|
+------------------------------------------------+EVENT TIME:        21:00[EST]|
| NRC NOTIFIED BY:  STEVE MORRISSEY              |LAST UPDATE DATE:  02/21/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIM TRAPP            R1      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| ELEVEN DEAD SEA DUCKS FOUND IN CIRCULATING WATER SCREEN WASH DEBRIS          |
|                                                                              |
| Eleven dead sea ducks were observed in Seabrook station's circulating water  |
| screen wash debris on February 20, 1999 at approximately 2100 hours.  It is  |
| not known at this time whether the ducks were alive or dead upon entering    |
| the offshore intake structure.  Sea ducks are diving birds which feed        |
| underwater.  This is a 24 hour notification in accordance with section 4.1   |
| of the environmental protection plan, appendix B of the operating license.   |
|                                                                              |
| The NRC resident inspector was notified of this event report by the          |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35391       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 02/21/1999|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 22:25[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        02/21/1999|
+------------------------------------------------+EVENT TIME:        20:50[CST]|
| NRC NOTIFIED BY:  HANKS                        |LAST UPDATE DATE:  02/21/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LAWRENCE YANDELL     R4      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR WAS MANUALLY SCRAMMED FROM 100% POWER DUE TO LOSS OF CONDENSER       |
| VACUUM.                                                                      |
|                                                                              |
| THE "A" MAIN CONDENSER HAD A SEAL FAILURE ON THE EXPANSION JOINT WHICH       |
| RESULTED IN A DECREASE  AND LOSS OF CONDENSER VACUUM.  DUE TO THIS           |
| CONDITION,  A MANUAL SCRAM WAS INITIATED FOLLOWED BY A MAIN TURBINE TRIP.    |
| THE CONTROLLED SHUTDOWN HAD NO IMMEDIATE PROBLEMS.  ALL RODS FULLY INSERTED. |
| NO ECCS ACTUATIONS OCCURRED.  THE LICENSEE ANTICIPATES THAT REACTOR VESSEL   |
| PRESSURE MAY BE LATER CONTROLLED VIA THE RELIEF VALVES DEPENDING ON THE      |
| COOLDOWN RATE (REACTOR VESSEL PRESSURE  IS CURRENTLY  550 LBS).  THE CURRENT |
| HEAT SINK  IS THE MAIN CONDENSER, BUT THE LICENSEE IS  PREPARING TO SHUT THE |
| MSIVs AND SHIFT THE HEAT SINK TO THE SUPPRESSION POOL.                       |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+