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Event Notification Report for July 26, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           07/23/1999 - 07/26/1999

                              ** EVENT NUMBERS **

31161  35867  35897  35948  35949  35950  35951  35952  35953  35954  35955  35956 
35957  35958  

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   31161       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  CAP ENGINEERING CONSULTANTS          |NOTIFICATION DATE: 10/16/1996|
|LICENSEE:  CAP ENGINEERING CONSULTANTS          |NOTIFICATION TIME: 15:14[EDT]|
|    CITY:  CORAL GABLES             REGION:  2  |EVENT DATE:        10/15/1996|
|  COUNTY:  POLK                      STATE:  FL |EVENT TIME:        00:00[EDT]|
|LICENSE#:  FL-2611-1             AGREEMENT:  Y  |LAST UPDATE DATE:  07/23/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CAUDLE JULIAN        RDO     |
|                                                |                             |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  REGION 2 (WOODRUFF)          |                             |
|  HQ OPS OFFICER:  RUDY KARSCH                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CAP ENGINEERING CONSULTANTS, CORAL GABLES, FL.                               |
|                                                                              |
| A TROXLER MODEL 3440 MOISTURE DENSITY GAGE WAS STOLEN FROM THE BACK OF A     |
| PICKUP TRUCK.  THE GAGE CONTAINED 9 mCi OF CESIUM-137 AND 44 mCi OF Am-Be.   |
| THE LICENSEE HOLDS A FLORIDA LICENSE AND REPORTED THE INCIDENT TO FLORIDA ON |
| 10/15/96.  REGION 2 (WOODRUFF) REPORTED THE EVENT TO THE OPERATIONS  CENTER. |
| REGION 2 IS ISSUING PN-072.                                                  |
|                                                                              |
| *  *  * UPDATE AT 1405 ON 07/23/99 FROM EAKINS TO CHAUNCEY GOULD *  *  *     |
|                                                                              |
| THE STATE OF FLORIDA BUREAU OF RADIATION CONTROL WAS INFORMED ON 07/23/99    |
| THAT THE STOLEN TROXLER MOISTURE DENSITY GAGE HAD BEEN RECOVERED IN WEBSTER, |
| FL.  SEE EVENT #35949 FOR ADDITIONAL DETAILS.  THE NRC OPERATIONS OFFICER    |
| NOTIFIED R2DO (ED McALPINE) AND NMSS EO (DON COOL).                          |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35867       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 06/26/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 05:28[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        06/26/1999|
+------------------------------------------------+EVENT TIME:        04:03[EDT]|
| NRC NOTIFIED BY:  DOUGLAS AMTSFIELD            |LAST UPDATE DATE:  07/23/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GLENN MEYER          R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM INOPERABLE                     |
|                                                                              |
| On 6-26-99 at 0403, the Unit 2 HPCI System was declared inoperable following |
| performance of a routine test on the HPCI drain pot orifice. The purpose of  |
| the test is to verify flow through the HPCI turbine exhaust drain pot        |
| discharge line flow orifice.  At the time of the failure the HPCI System was |
| operable.  The HPCI System was conservatively declared inoperable due to the |
| potential for the exhaust line to fill.                                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 1449 EDT ON 07/23/99 FROM STANLEY GAMBLE TO S. SANDIN * * *  |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| The HPCI System was conservatively declared inoperable due to the potential  |
| for water to be present in the turbine as a result of a plugged flow orifice |
| on the turbine exhaust drain pot drain line.  The plugged orifice was        |
| discovered during performance of a test specifically designed to ensure that |
| exhaust drain pot drain line flow path is operable.  Testing is routinely    |
| scheduled the day following normal HPCI System surveillance testing since    |
| operation of the HPCI System is the initiator for plugging of the flow       |
| orifice.                                                                     |
|                                                                              |
| The basis for this retraction is that a minimal amount, less than one        |
| gallon, of condensate was drained from the exhaust drain pot when the flow   |
| orifice piping was disassembled.  The amount of condensate was much less     |
| than the amount required to adversely impact HPCI System operability.  It    |
| would require in excess of 40 gallons of condensate to fill the exhaust      |
| drain pot to a level that would result in condensate entering the turbine or |
| exhaust line.  Therefore, the HPCI System was operable and capable of        |
| performing its safety function until it was removed from service to clear    |
| the flow orifice.                                                            |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
|                                                                              |
| The NRC Operations Officer notified R1DO (Jim Noggle).                       |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35897       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 07/06/1999|
|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 02:44[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        07/06/1999|
+------------------------------------------------+EVENT TIME:        02:04[EDT]|
| NRC NOTIFIED BY:  LISA HILBERT-SEMMES          |LAST UPDATE DATE:  07/23/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PAUL FREDRICKSON     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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Hot Shutdown     |0        Intermediate Shut|
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MODE CHANGE INITIATED AS PART OF A TECHNICAL SPECIFICATION REQUIRED          |
| SHUTDOWN                                                                     |
|                                                                              |
| "At 1810 hours on 7-5-99, with Surry Power Station Unit 2 at Hot Shutdown    |
| (HSD) following a reactor trip, the 'A' Cold Leg Loop Stop Valve (Mark       |
| number 2-RC-MOV-2591) was removed from it's backseat in accordance with      |
| station procedure 2-GOP-2.4.  Upon reopening the valve, full open indication |
| was not received.  In accordance with Technical Specification 3.17.1 and     |
| 3.0.1, a 30 hour clock to Cold Shutdown (CSD) LCO was started.  The valve    |
| was de-energized by opening it's breaker.  A cooldown to CSD was initiated   |
| at 2050 on 7-5-99.  At 0204 on 7-6-99, a review of Station procedures and    |
| 10CFR50.72 determined that a one hour report was required for commencing the |
| RCS cooldown in accordance with the Technical Specification LCO.             |
|                                                                              |
| "There were no radiation releases due to this event, nor were there any      |
| personnel injuries or contamination events.                                  |
|                                                                              |
| "Unit 2 is currently in Intermediate Shutdown with RCS cooldown in progress  |
| in accordance with station procedures.                                       |
|                                                                              |
| "Unit 1 was not affected by this event and remains stable at 100% power and  |
| 824 MWe.                                                                     |
|                                                                              |
| "This event is being reported in accordance with 10CFR50.72(b)(1)(i)(A)."    |
|                                                                              |
| The Licensee informed the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE AT 0940 ON 07/23/99 FROM RAWLEIGH DILLARD TO JOLLIFFE * * *     |
|                                                                              |
| A review of NUREG 1022 with respect to 10CFR50.72(b)(1)(i)(A) provides the   |
| following clarification: "the phrase 'initiation of any nuclear plant        |
| shutdown' includes action to start reducing reactor power, i.e., adding      |
| negative reactivity to achieve a nuclear plant shutdown required by          |
| Technical Specifications.  The 'initiation of any nuclear plant shutdown'    |
| does not include mode changes required by Technical Specifications if        |
| initiated after the plant is already in a shutdown condition."               |
|                                                                              |
| Unit 2 achieved Hot Shutdown Mode at 1122 on 07/05/99 after a reactor trip.  |
| Based on the information given above in NUREG 1022, a one hour report was    |
| not required for commencing the cooldown to Cold Shutdown Mode as this was a |
| mode change after Unit 2 was already in a shutdown condition.  The actions   |
| taken by the Licensee were prudent and represented a conservative decision   |
| by the Licensee.                                                             |
|                                                                              |
| Thus, the Licensee desires to retract the above report based on the above    |
| discussion.                                                                  |
|                                                                              |
| The Licensee informed the NRC Resident Inspector.                            |
|                                                                              |
| The NRC Operations Officer notified the R2DO Ed McAlpine.                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35948       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  OR DEPT OF HEALTH RAD PROTECTION     |NOTIFICATION DATE: 07/23/1999|
|LICENSEE:  EUGENE SAND AND GRAVEL COMPANY       |NOTIFICATION TIME: 12:06[EDT]|
|    CITY:  EUGENE                   REGION:  4  |EVENT DATE:        07/22/1999|
|  COUNTY:                            STATE:  OR |EVENT TIME:        16:26[PDT]|
|LICENSE#:  ORE-90643             AGREEMENT:  Y  |LAST UPDATE DATE:  07/23/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ELMO COLLINS         R4      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  WRIGHT                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TROXLER MOISTURE DENSITY GAUGE DAMAGED AT A FLORENCE, OR. JOBSITE            |
|                                                                              |
| A TROXLER MOISTURE DENSITY GAUGE SERIES 3400 CONTAINING 9 MILLICURIES OF     |
| CESIUM-137 AND 44 MILLICURIES OF AMERICIUM-241-BERYLLIUM WAS RUN OVER BY A   |
| PICKUP TRUCK.  THE SOURCE ROD WAS IN THE STORAGE POSITION WHEN THE DEVICE    |
| WAS RUN OVER.  THE ONLY DAMAGE APPEARS TO BE TO THE ELECTRONICS PORTION OF   |
| THE DEVICE.  A PRELIMINARY SWIPE WAS TAKEN AND NO CONTAMINATION WAS          |
| DETERMINED.  THE DEVICE IS BEING STORED AT THE LICENSEE'S FACILITY IN        |
| EUGENE, OREGON AWAITING TO BE SENT BACK TO THE MANUFACTURER.                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35949       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FLORIDA STATE WARNING POINT          |NOTIFICATION DATE: 07/23/1999|
|LICENSEE:  CAP ENGINEERING CONSULTANTS          |NOTIFICATION TIME: 12:46[EDT]|
|    CITY:  WEBSTER                  REGION:  2  |EVENT DATE:        07/23/1999|
|  COUNTY:  SUMTER                    STATE:  FL |EVENT TIME:        12:00[EDT]|
|LICENSE#:  FL-2611-1             AGREEMENT:  Y  |LAST UPDATE DATE:  07/23/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |EDWARD MCALPINE      R2      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  FLETCHER                     |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TROXLER MOISTURE DENSITY GAUGE FOUND IN WEBSTER, FL                          |
|                                                                              |
| MELISSA SYLVEST, FL STATE WARNING POINT, REPORTED TO THE NATIONAL RESPONSE   |
| CENTER THAT A TROXLER MOISTURE DENSITY GAUGE, SERIAL #26065, WAS FOUND BY    |
| THE ROAD SIDE IN WEBSTER, FL.  THE DEVICE DOES NOT APPEAR TO BE DAMAGED AND  |
| IS BEING HELD BY THE WEBSTER POLICE DEPARTMENT.  THE LICENSEE FOR THE DEVICE |
| IS CAP ENGINEERING CONSULTANTS.                                              |
|                                                                              |
| NATIONAL RESPONSE CENTER INCIDENT REPORT #492446.                            |
|                                                                              |
| SEE EVENT #31161 FOR ADDITIONAL INFORMATION.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35950       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 07/23/1999|
|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 12:51[EDT]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        07/23/1999|
+------------------------------------------------+EVENT TIME:        11:30[EDT]|
| NRC NOTIFIED BY:  T. McKEE                     |LAST UPDATE DATE:  07/23/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES NOGGLE         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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION OF A MINOR SEWAGE SPILL                                 |
|                                                                              |
| The licensee notified the New York State Department of Environmental         |
| Conservation of a 2-5 gallon sewage spill from the warehouse sewage pit to a |
| storm drain.                                                                 |
|                                                                              |
| The licensee will inform the NRC Resident Inspector.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35951       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NEW YORK CITY DEPT OF HEALTH         |NOTIFICATION DATE: 07/23/1999|
|LICENSEE:  NEW YORK PRESBYTERIAN HOSPITAL       |NOTIFICATION TIME: 13:20[EDT]|
|    CITY:  NEW YORK                 REGION:  1  |EVENT DATE:        07/22/1999|
|  COUNTY:                            STATE:  NY |EVENT TIME:        13:20[EDT]|
|LICENSE#:  52-2960-11            AGREEMENT:  Y  |LAST UPDATE DATE:  07/23/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JAMES NOGGLE         R1      |
|                                                |SCOTT MOORE          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  BORRI                        |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MISSING SHIPMENT OF 10 MILLICURIES OF IODINE-131                             |
|                                                                              |
| NEW YORK PRESBYTERIAN HOSPITAL, NEW YORK CITY,  RECEIVED A SHIPMENT OF 10    |
| MILLICURIES OF IODINE -131 ON 07/20/99 FROM MDS NORDIAN, CANADA.  THE SOURCE |
| APPEARS TO BE MISSING AS OF 07/22/99.  HOSPITAL PERSONNEL ARE SEARCHING FOR  |
| THE SHIPMENT AT THE HOSPITAL.                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35952       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 07/23/1999|
|    UNIT:  [1] [2] []                STATE:  VA |NOTIFICATION TIME: 13:26[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        07/19/1999|
+------------------------------------------------+EVENT TIME:        09:45[EDT]|
| NRC NOTIFIED BY:  MIKE WHALEN                  |LAST UPDATE DATE:  07/23/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |EDWARD MCALPINE      R2      |
|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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| A LICENSEE VOLUNTARY 24 HOUR NOTIFICATION IS BEING MADE TO REPORT AN INITIAL |
| LACK OF INDEPENDENT ANALYSIS OF BORON CONCENTRATION SAMPLES.                 |
|                                                                              |
| Dissolved boron concentration of the spent fuel pool and of the water added  |
| to the cavity of a sealed source storage cask is required to be within       |
| limits specified in ISFSI Technical Specification Section 3.2.1, Table 3-1   |
| within 4 hours prior to commencing loading operations. The boron             |
| concentration is determined using chemical analysis of two samples analyzed  |
| by different individuals to reduce the risk that a single error could lead   |
| to not meeting the LCO.                                                      |
|                                                                              |
| By procedure, Sample 1 is obtained from the spent fuel pool and from the     |
| cask pit by one technician.  Sample 2 is then obtained from the spent fuel   |
| pool and from the cask pit by a different technician.  Sample 1 is to be     |
| analyzed by the technician who obtained Sample 2 and vice versa.             |
|                                                                              |
| On 07/19/99, boron concentration sampling was performed prior to loading a   |
| spent fuel cask.  Technician 1 obtained both cask pit samples and Technician |
| 2 obtained both spent fuel pool samples. Technician 1 then analyzed both     |
| cask pit samples and Technician 2 analyzed both spent fuel pool samples.     |
| This is contrary to ISFSI Technical Specification Section 3.2.1.  Upon       |
| realizing the lack of independence in analyzing the samples, Technician 1    |
| analyzed the samples Technician 2 obtained and vice versa.  Results of the   |
| analysis indicated acceptable dissolved boron concentrations.                |
|                                                                              |
| The Licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35953       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  OR DEPT OF HEALTH RAD PROTECTION     |NOTIFICATION DATE: 07/23/1999|
|LICENSEE:  SMURFIT NEWSPRINT COMPANY            |NOTIFICATION TIME: 14:52[EDT]|
|    CITY:  OREGON CITY              REGION:  4  |EVENT DATE:        07/07/1999|
|  COUNTY:                            STATE:  OR |EVENT TIME:        10:49[PDT]|
|LICENSE#:  ORE-90296             AGREEMENT:  Y  |LAST UPDATE DATE:  07/23/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ELMO COLLINS         R4      |
|                                                |SCOTT MOORE          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  WRIGHT                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| STUCK SHUTTER ON A K-RAY LEVEL DETECTOR                                      |
|                                                                              |
| ON 07/16/99, A SMURFIT NEWSPRINT COMPANY REPRESENTATIVE NOTIFIED THE OREGON  |
| DEPARTMENT OF HEALTH RADIATION PROTECTION THAT THE SHUTTER ON A MODEL 7062B  |
| K-RAY LEVEL DETECTOR AT THE SMURFIT NEWSPRINT COMPANY FACILITY IN OREGON     |
| CITY, OREGON STUCK OPEN FOR UNKNOWN REASONS.  THE DETECTOR IS LOCATED IN THE |
| #5 TMP STEAMING TUBE/TANK WHICH IS USED FOR PROCESSING PAPER.  A TN          |
| TECHNOLOGIES REPRESENTATIVE WILL GO TO THE PLANT TO REPLACE THE DETECTOR.    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35954       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 07/23/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 17:04[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        07/23/1999|
+------------------------------------------------+EVENT TIME:        15:58[EDT]|
| NRC NOTIFIED BY:  SIENCZAK                     |LAST UPDATE DATE:  07/23/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES NOGGLE         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     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTO REACTOR SCRAM FROM 100% POWER DUE TO A HIGH FLUX SIGNAL                 |
|                                                                              |
| DURING POST MAINTENANCE TESTING OF THE MECHANICAL PRESSURE REGULATOR,        |
| REACTOR PRESSURE OSCILLATIONS WERE EXPERIENCED AND AN AUTOMATIC REACTOR      |
| SCRAM OCCURRED FROM 100% POWER DUE TO A HIGH FLUX SIGNAL.  ALL CONTROL RODS  |
| FULLY INSERTED AND NO SAFETY/RELIEF VALVES LIFTED.  THE HIGH PRESSURE        |
| COOLANT INJECTION SYSTEM STARTED AS EXPECTED AND INJECTED FOR APPROXIMATELY  |
| 52 SECONDS BEFORE BEING SECURED.  UNIT 1 IS STABLE IN HOT SHUTDOWN CONDITION |
| AND COOLDOWN IS IN PROGRESS.  ALL SYSTEMS APPEARED TO FUNCTION, AS           |
| DESIGNED.                                                                    |
|                                                                              |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35955       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 07/23/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 22:06[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        07/23/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        03:20[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  07/23/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |PATRICK HILAND       R3      |
|  DOCKET:  0707002                              |LARRY CAMPER         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM McCLEERY                 |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBA 76.120(c)(2)(i)     ACCID MT EQUIP FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC SHUTDOWN OF AUTOCLAVE #2 STEAM SYSTEM DUE TO HIGH CONDENSATE       |
| LEVEL                                                                        |
|                                                                              |
| AT 0320 ON 07/23/99, AUTOCLAVE #2, OPERATING IN MODE 2 (HEATING),            |
| EXPERIENCED A SAFETY SYSTEM SHUTDOWN WHEN BOTH CONDENSATE HIGH LEVEL PROBES  |
| ALARMED SHUTTING DOWN THE STEAM SYSTEM 20 MINUTES INTO THE HEATING CYCLE.    |
| THIS ACTUATION PLACED THE AUTOCLAVE INTO MODE 7 (SHUTDOWN) AND WAS DECLARED  |
| INOPERABLE BY THE PLANT SHIFT SUPERINTENDENT AT 0331.  OPERATIONS PERSONNEL  |
| FOLLOWED ESTABLISHED ALARM RESPONSE PROCEDURES AND VERIFIED THE HIGH LEVEL   |
| ALARM ACTUATION AT 0430.   AN ENGINEERING EVALUATION IS IN PROGRESS.         |
|                                                                              |
| THERE WAS NO LOSS OF HAZARDOUS OR RADIOACTIVE MATERIAL NOR RADIOACTIVE OR    |
| RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT.               |
|                                                                              |
| THE NRC RESIDENT INSPECTOR AND THE DOE SITE REPRESENTATIVE HAVE BEEN         |
| NOTIFIED.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35956       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 07/24/1999|
|    UNIT:  [] [2] [3]                STATE:  IL |NOTIFICATION TIME: 13:34[EDT]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        07/24/1999|
+------------------------------------------------+EVENT TIME:        09:20[CDT]|
| NRC NOTIFIED BY:  GADBOIS                      |LAST UPDATE DATE:  07/24/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PATRICK HILAND       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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       57       Power Operation  |57       Power Operation  |
|3     N          Y       68       Power Operation  |68       Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO ILLINOIS EPA                                         |
|                                                                              |
| THE LICENSEE NOTIFIED THE ILLINOIS EPA AS REQUIRED BY NPDES PERMIT STANDARD  |
| CONDITION NO. 12(e)(1) OF AN UNANTICIPATED BYPASS OF THE DRESDEN STATION     |
| COOLING POND.  THIS OCCURRED DUE TO A LIGHTNING STRIKE THAT CAUSED THE LOSS  |
| OF THE COOLING POND LIFT STATION.  THE COOLING POND WAS PLACED ON BYPASS AT  |
| 2241 CDT ON 07/23/99.  LIFT STATION OPERATION WAS RESTORED AND THE COOLING   |
| POND PLACED BACK ON INDIRECT OPEN CYCLE AT 0626 CDT ON 07/24/99.  BOTH UNITS |
| WERE PREVIOUSLY DERATED DUE TO THERMAL DISCHARGE LIMITATIONS.                |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35957       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS           REGION:  1  |NOTIFICATION DATE: 07/24/1999|
|    UNIT:  [1] [] []                 STATE:  MD |NOTIFICATION TIME: 15:16[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        07/24/1999|
+------------------------------------------------+EVENT TIME:        14:38[EDT]|
| NRC NOTIFIED BY:  PACE                         |LAST UPDATE DATE:  07/24/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JAMES NOGGLE         R1      |
|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     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTO REACTOR TRIP FROM 100% POWER FOLLOWING A TURBINE TRIP.                  |
|                                                                              |
| AN AUTO REACTOR TRIP OCCURRED FROM 100% POWER FOLLOWING A TURBINE TRIP WHICH |
| OCCURRED FOLLOWING LOSS OF UNIT TRANSFORMER U25,000-12.  IT APPEARS THAT THE |
| TRANSFORMER FAULT PROTECTION ACTUATED DUE TO A POSSIBLE LIGHTNING STRIKE TO  |
| THE TRANSFORMER.  THE FIRE DELUGE SYSTEM FOR THE TRANSFORMER ACTUATED, BUT   |
| THERE WAS NO EVIDENCE OF ANY FIRE, WITH THE EXCEPTION OF A SCORCHED PHASE    |
| BUSHING WHICH MAY HAVE BEEN THE RESULT OF A LIGHTNING STRIKE.  THERE IS NO   |
| ESTIMATE OF THE EXTENT OF DAMAGE TO THE TRANSFORMER.  ALL CONTROL RODS FULLY |
| INSERTED, NO ECCS INJECTION OCCURRED AND NO SAFETY/RELIEF VALVES APPEARED TO |
| HAVE LIFTED.  THE CURRENT HEAT SINK IS THE MAIN CONDENSER.                   |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35958       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE: 07/25/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 22:32[EDT]|
|   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:        07/25/1999|
+------------------------------------------------+EVENT TIME:        20:21[CDT]|
| NRC NOTIFIED BY:  WILLIAMS                     |LAST UPDATE DATE:  07/25/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PATRICK HILAND       R3      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(1)(ii)(A)  UNANALYZED COND OP     |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       87       Power Operation  |87       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PLANT ENTERED TECH SPEC 3.2.3 LCO ACTION STATEMENT                           |
|                                                                              |
| AT 2021 CDT ON 07/25/99, THE "1B21-N500" PRESSURE TRANSMITTER INDICATION     |
| DROPPED FROM 1000 PSIG TO INDICATED 600 PSIG REACTOR PRESSURE.  THIS         |
| TRANSMITTER IS THE PRIMARY PRESSURE TRANSMITTER TO THE ELECTROHYDRAULIC      |
| SYSTEM (EHC).  DUE TO THIS CHANGE IN PRESSURE INDICATION, THE BACKUP         |
| TRANSMITTER TOOK CONTROL.  IN THIS LINEUP (BACKUP TRANSMITTER IN CONTROL OF  |
| THE EHC), THERE IS NO OTHER BACKUP TRANSMITTER AVAILABLE AND PROCEDURE       |
| "LOA-EH-101" STATES THAT THIS CONDITION IS AN UNANALYZED CONDITION AND THE   |
| PLANT IS TO ENTER TS 3.2.3.  TS 3.2.3 REQUIRES THE REACTOR TO BE <25% POWER  |
| WITHIN 4 HOURS.  THIS CONDITION WAS NOT DETERMINED TO BE AN UNANALYZED       |
| CONDITION UNTIL 2045 CDT ON 07/25/99 UTILIZING THE ABOVE PROCEDURE AND THE   |
| UFSAR.  THE PROBLEM WITH THE TRANSMITTER IS BEING INVESTIGATED TO DETERMINE  |
| WHY IT DOES NOT INDICATE 1000 PSIG.                                          |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE INFORMED.                                     |
+------------------------------------------------------------------------------+