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Event Notification Report for June 23, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/22/2000 - 06/23/2000

                              ** EVENT NUMBERS **

37031  37095  37102  37103  37104  37105  37106  37107  37108  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37031       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 05/25/2000|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 09:21[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        05/25/2000|
+------------------------------------------------+EVENT TIME:        08:32[EDT]|
| NRC NOTIFIED BY:  KEVIN PHILLIPS               |LAST UPDATE DATE:  06/22/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK LESSER          R2      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUXILIARY BUILDING FILTERED EXHAUST MAY NOT HAVE BEEN ABLE TO PERFORM ITS    |
| DESIGN FUNCTION                                                              |
|                                                                              |
| The licensee discovered both doors on the vestibule to the '1A' Centrifugal  |
| Charging Pump Room not fully closed, this may have prevented the Auxiliary   |
| Building filtered exhaust system from maintaining a negative pressure in     |
| that room.  This would render both trains of Auxiliary Building exhaust      |
| inoperable per Technical Specifications 3.7.12 and would require entry into  |
| Technical Specification 3.0.3.  The doors were closed on discovery which     |
| returned the unit to compliance with Technical Specifications.               |
|                                                                              |
| The licensee will followup with an investigation into when and how the doors |
| came to be open.                                                             |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * *  UPDATE ON 6/22/00 @ 1610 BY BURGESS TO GOULD * * *  RETRACTION        |
|                                                                              |
| After further engineering evaluation, it has been determined that the plant  |
| was not outside the design basis during this event.  Therefore, this         |
| notification is being retracted.                                             |
|                                                                              |
| The NRC Resident Inspector will be notified by the licensee.                 |
|                                                                              |
| The Reg 2 RDO (Landis) was informed by the NRC Operations Officer.           |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37095       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DAVIS BESSE              REGION:  3  |NOTIFICATION DATE: 06/19/2000|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 16:22[EDT]|
|   RXTYPE: [1] B&W-R-LP                         |EVENT DATE:        06/19/2000|
+------------------------------------------------+EVENT TIME:        15:25[EDT]|
| NRC NOTIFIED BY:  CRAIG GILLIG                 |LAST UPDATE DATE:  06/22/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |98       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT SHUTDOWN REQUIRED BY TECH SPEC 3.0.3 DUE TO FAILED VALVE TESTING       |
|                                                                              |
| The licensee was conducting Instrument and Control testing under DB-MI-03211 |
| which failed to produce the expected response for solenoid SP6A2 on valve    |
| SP6A, Steam Generator Main Feedwater Valve.  The problem is with the         |
| solenoid or associated limit switch.  Due to a lack of specific Technical    |
| Specification guidance, 3.0.3 has been entered which requires the plant to   |
| initiate action to place the plant in a mode in which the specification does |
| not apply.  It is expected that the plant will be able to repair and test    |
| prior to a full plant shutdown.                                              |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 1710 EST ON 6/19/00 BY CRAIG GILLIG TO FANGIE JONES * * *    |
|                                                                              |
| The licensee determined the problem was with the limit switch, has exited    |
| the tech spec required shutdown, and is returning to full power from 96%.    |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.  The R3DO (Roger  |
| Lanksbury) has been notified.                                                |
|                                                                              |
| * * * UPDATE ON 6/22/00 @ 1334 BY WOLF TO GOULD * * *   RETRACTION           |
|                                                                              |
| The suspect limit switch for solenoid valve SVSP6A2 has been adjusted and    |
| satisfactorily tested via Surveillance Test DB-MI-03211. This testing        |
| confirmed that the problem was only with the limit switch. The solenoid      |
| valve and associated Steam Generator Main Feedwater Control Valve SPGA       |
| remained operable during this event. Therefore, the plant was not in the     |
| Action Statement for Technical Specification 3.0.3, and no plant shutdown    |
| was required. Therefore, the licensee desires to retract this event.         |
|                                                                              |
| The NRC Resident Inspector has been notified of the retraction by the        |
| licensee.                                                                    |
|                                                                              |
| The Reg 3 RDO (Lanksbury) was informed by the NRC Operations Officer.        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37102       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 06/22/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 09:57[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        06/22/2000|
+------------------------------------------------+EVENT TIME:        07:28[CDT]|
| NRC NOTIFIED BY:  JOHN WASHKO                  |LAST UPDATE DATE:  06/22/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       98       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - AUTO REACTOR SCRAM FROM 98% POWER CAUSED BY LOSS OF REACTOR FEEDWATER PUMP |
| -                                                                            |
|                                                                              |
| At 0728 CDT on 06/22/00, LaSalle Unit 2 experienced an automatic reactor     |
| scram from 98% power due to low reactor vessel water level (+12.5 inches,    |
| Level 3).  Normal reactor vessel water level is +36 inches.  The low reactor |
| vessel water level was caused by a loss of the #2A turbine driven reactor    |
| feedwater pump for unknown reasons.  The lowest reactor vessel water level   |
| reached was -23 inches on the wide range recorders.  All control rods        |
| inserted completely.  Steam is being dumped to the main condenser.  No       |
| emergency core cooling system actuations occurred or were required during    |
| the transient.  All systems operated as designed with the exception of the   |
| Unit 2 station air compressor, which went into a surge condition. The air    |
| compressor has been secured and the Unit 0 station air compressor was        |
| started to pick up the additional load.  Unit 2 is stable in Condition 3     |
| (Hot Shutdown) with reactor vessel water level and pressure being maintained |
| in their normal bands.  The licensee is investigating the cause of the #2A   |
| reactor feedwater pump loss.                                                 |
|                                                                              |
| This event had no effect on Unit 1 which is at 100% power.                   |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37103       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  OHIO BUREAU OF RADIATION PROTECTION  |NOTIFICATION DATE: 06/22/2000|
|LICENSEE:  DAVID V. LEWIN CORPORATION           |NOTIFICATION TIME: 11:18[EDT]|
|    CITY:  TWINSBURG                REGION:  3  |EVENT DATE:        06/21/2000|
|  COUNTY:                            STATE:  OH |EVENT TIME:        10:00[EDT]|
|LICENSE#:  31-210180022          AGREEMENT:  Y  |LAST UPDATE DATE:  06/22/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ROGER LANKSBURY      R3      |
|                                                |JOSIE PICCONE        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MIKE SNEE                    |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|NDAM                     DAMAGED GAUGE/DEVICE   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - DAMAGED CPN PORTABLE MOISTURE DENSITY GAUGE         |
|                                                                              |
| At 1000 on 06/21/00, a CPN portable moisture density gauge belonging to      |
| David V. Lewin Corporation, Cleveland, OH, was damaged at a construction     |
| site at State Route 91 a mile north of Twinsburg, OH.  The gauge had been    |
| struck by a backhoe while the Cs-137 source was extended from the gauge.     |
| The gauge is a CPN model MC3 containing a 10 mCi Cs-137 source and a 50 mCi  |
| Am-241 source.  The gauge was damaged in a way that prevented the Cs-137     |
| source from being secured in the safe position.  The licensee contacted CTS, |
| license #03225230000, a licensed gauge repair facility for advice.  Ohio     |
| Department of Health inspectors were dispatched to the site to monitor the   |
| recovery.                                                                    |
|                                                                              |
| CTS recommended that the guide tube be cut which would allow the Cs-137      |
| source to be retracted into the safe position.  The guide tube was cut and   |
| the source was secured in the safe position.  The source was not damaged and |
| no contamination was detected.  Dose rates with the source extended were 350 |
| mrem/hr.                                                                     |
|                                                                              |
| The gauge was taken back to the David V. Lewin Corporation and will be       |
| shipped to CTS for evaluation and possible repair.  The licensee will issue  |
| a report to the Ohio Department of Health within 30 days.                    |
|                                                                              |
| Ohio Report #00-019.                                                         |
|                                                                              |
| Mike Snee notified NRC Region 3 Jim Lynch.                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   37104       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  GEORGE WASHINGTON UNIV. HOSPITAL     |NOTIFICATION DATE: 06/22/2000|
|LICENSEE:  GEORGE WASHINGTON UNIV. HOSPITAL     |NOTIFICATION TIME: 16:51[EDT]|
|    CITY:  WASHINGTON               REGION:  1  |EVENT DATE:        06/14/2000|
|  COUNTY:                            STATE:  DC |EVENT TIME:        14:30[EDT]|
|LICENSE#:  08-00216-22           AGREEMENT:  N  |LAST UPDATE DATE:  06/22/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ROBERT SUMMERS       R1      |
|                                                |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOHNSON                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|LADM 35.33(a)            MED MISADMINISTRATION  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| GEORGE WASHINGTON UNIVERSITY HOSPITAL REPORTED AN UNDERTREATMENT DURING      |
| BRACHYTHERAPY.                                                               |
|                                                                              |
| THE HOSPITAL REPORTED THAT A FEMALE PATIENT WAS BEING TREATED WITH CESIUM    |
| 137 SEEDS IN THE FIRST OF A TWO PHASE TREATMENT SEQUENCE WITH EACH           |
| DELIVERING APPROXIMATELY 1,680 RADS.  DURING THIS TREATMENT THE DEVICE THAT  |
| CONTAINED THE SEEDS SLIPPED OUT OF THE AREA BEING TREATED.  IT IS NOT KNOWN  |
| WHEN THIS ACTUALLY OCCURRED, BUT THE UNDERTREATMENT COULD HAVE LASTED        |
| BETWEEN 3.25 - 6 HOURS.  THEY ARE ESTIMATING THAT THE PATIENT MAY HAVE ONLY  |
| RECEIVED 1,478.5 RADS.  A CORRECTION FOR THIS UNDERTREATMENT CAN BE DONE     |
| DURING THE SECOND PHASE.  THERE ALSO MAY HAVE BEEN OTHER AREAS NOT DESTINED  |
| FOR TREATMENT THAT WERE EXPOSED TO THE RADIATION WHEN THE DEVICE SLIPPED.    |
| THE PATIENT HAS BEEN REEXAMINED A WEEK FOLLOWING THIS MISADMINISTRATION AND  |
| NO ADVERSE AFFECTS WERE DETERMINED.  A SECOND FOLLOWUP EXAMINATION WILL BE   |
| DONE WITHIN A WEEK.  THE PATIENT WAS INFORMED AND THE ATTENDING PHYSICIAN    |
| WAS NOTIFIED.                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37105       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 06/22/2000|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 17:26[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        06/22/2000|
+------------------------------------------------+EVENT TIME:        15:13[CDT]|
| NRC NOTIFIED BY:  GILMORE                      |LAST UPDATE DATE:  06/22/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOE TAPIA            R4      |
|10 CFR SECTION:                                 |FRANK CONGEL         IRO     |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LICENSEE ISSUED THE FOLLOWING PRESS RELEASE REGARDING A FIRE IN A PLANT  |
| SUPPORT BUILDING:                                                            |
|                                                                              |
| "BURLINGTON, KS - A small, localized fire occurred early this afternoon at   |
| Wolf Creek Generating Station. The fire was contained in the welding area of |
| a support building about 150 yards from where electricity is generated. The  |
| fire appears to have originated from an equipment malfunction.               |
|                                                                              |
| No injuries were reported.                                                   |
|                                                                              |
| The plant's fire brigade responded and with assistance from the Coffey       |
| County Fire Department, quickly extinguished the fire. The fire was          |
| extinguished at about 1:41 p.m.                                              |
|                                                                              |
| The equipment, a plasma-arc cutter, is used to cut metal such as stainless   |
| steel. Workers were cutting one and one-half inch stainless when the fire    |
| started.                                                                     |
|                                                                              |
| Wolf Creek Nuclear Operating Corporation operates Wolf Creek Generating      |
| Station near Burlington, Kan.                                                |
| Wolf Creek is owned by Kansas City Power & Light Company; KGE, a Western     |
| Resources Company; and                                                       |
| Kansas Electric Power Cooperative, inc. The plant is in Coffey County,       |
| Kansas, about four miles northeast of                                        |
| Burlington. The plant is 55 miles south of Topeka, 90 miles southwest of     |
| Kansas City, and 120 miles northeast                                         |
| of Wichita."                                                                 |
|                                                                              |
| The fire lasted for approximately 20 minutes (1321-1341 CDT) and the only    |
| damage was to the piece of equipment.                                        |
|                                                                              |
| The NRC Resident Inspector was notified by the licensee.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37106       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 06/22/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 17:43[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        06/22/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:00[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  06/22/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |ROGER LANKSBURY      R3      |
|  DOCKET:  0707002                              |ROBERT PIERSON       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  HALCOMB                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| At 1100 hours on 06/22/00, it was determined by the Plant Shift              |
| Superintendent, Engineering, and Nuclear Regulatory Affairs that Criticality |
| Accident Alarm System Technical Safety Requirement (TSR) required actions    |
| were not entered as required. The concern was whether a TSR Limiting         |
| Condition for Operation (LCO) should be entered prior to performing Safety   |
| Analysis Review required horns and light testing.                            |
|                                                                              |
| All previous testing has correctly been accomplished under site operability  |
| procedures, even though no LCO actions were initiated due to taking credit   |
| for the nitrogen system. The issue was raised due to the fact that when the  |
| cascade strombos horns are sounding, the nitrogen horns could not be heard   |
| to meet required LCO requirements. Currently, all plant site Criticality     |
| Accident Alarm Systems are fully operable.                                   |
|                                                                              |
| This condition is reportable to the NRC per 10CFR76.120(c) "Safety Equipment |
| Failure/Actuation". The equipment is required by a TSR to be available and   |
| operable and no redundant equipment is available and operable to perform the |
| required safety function.                                                    |
|                                                                              |
| The DOE Site Representative and NRC Resident Inspector were notified by the  |
| licensee..                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37107       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 06/22/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 18:07[EDT]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        06/22/2000|
+------------------------------------------------+EVENT TIME:        14:07[CDT]|
| NRC NOTIFIED BY:  BORING                       |LAST UPDATE DATE:  06/22/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE PLANT ENTERED A 14 DAY LCO ACTION STATEMENT DUE TO HIGH PRESSURE COOLANT |
| INJECTION (HPCI) SYSTEM BEING DECLARED INOPERABLE.                           |
|                                                                              |
| During routine surveillance testing of the Containment Cooling Water System, |
| required system flow through the HPCI Room Cooler could not be obtained due  |
| to leakage past 2-3999-252 check valve.                                      |
|                                                                              |
| With the HPCI Room Cooler inoperable, the HPCI System was declared           |
| INOPERABLE, a 14 day LCO Action Statement was entered, and an action request |
| for repair of the 2-3999-252 valve was submitted.                            |
|                                                                              |
| The NRC Resident Inspector was notified by the licensee.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37108       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE               REGION:  4  |NOTIFICATION DATE: 06/22/2000|
|    UNIT:  [] [2] [3]                STATE:  CA |NOTIFICATION TIME: 21:40[EDT]|
|   RXTYPE: [1] W-3-LP,[2] CE,[3] CE             |EVENT DATE:        06/22/2000|
+------------------------------------------------+EVENT TIME:        16:16[PDT]|
| NRC NOTIFIED BY:  WILLIAMS                     |LAST UPDATE DATE:  06/22/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOE TAPIA            R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AT 1616 PDT ON 06/22/00, THE LICENSEE NOTIFIED THE CALIFORNIA OFFICE OF      |
| EMERGENCY SERVICES AND THE SAN DIEGO DEPARTMENT OF ENVIRONMENTAL HEALTH OF A |
| SODIUM HYPOCHLORIDE LEAK.                                                    |
|                                                                              |
| At 0830 PDT on 06/22/00, a 3 to 5 gpm leak occurred from the Unit 2 sodium   |
| hypochloride storage tank. As a precaution, the licensee evacuated           |
| nonessential personnel from the area of the leak. The spilled liquid was     |
| fully contained by a berm around the tank. This event did not pose a threat  |
| to the nuclear power plant or hamper site personnel in the performance of    |
| duties necessary for safe plant operation. Even though there was no threat   |
| to control room personnel and plant conditions did not require it, at 1005   |
| PDT, operators manually initiated Toxic Gas Isolation Signal (TGIS) as a     |
| precautionary measure in response to changing wind direction. (TGIS is       |
| designed to terminate the supply of outside air to the control room and      |
| initiate operation of the control room emergency HVAC system to minimize     |
| operator exposure.)  All system components operated as expected.             |
|                                                                              |
| The event was terminated at approximately 1145 PDT.  There were no           |
| injuries.                                                                    |
|                                                                              |
| The NRC Resident Inspector will be informed by the licensee.                 |
+------------------------------------------------------------------------------+