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Event Notification Report for April 26, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/23/1999 - 04/26/1999

                              ** EVENT NUMBERS **

35600  35612  35622  35623  35624  35625  35627  35628  35629  35630  35631 
35632  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35600       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 04/17/1999|
|    UNIT:  [] [] [3]                 STATE:  IL |NOTIFICATION TIME: 11:58[EDT]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        04/17/1999|
+------------------------------------------------+EVENT TIME:        09:59[CDT]|
| NRC NOTIFIED BY:  DAVE SLAGER                  |LAST UPDATE DATE:  04/23/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN JACOBSON        R3      |
|10 CFR SECTION:                                 |                             |
|ADEG 50.72(b)(1)(ii)     DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          Y       99       Power Operation  |99       Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FAILURE OF A PRIMARY CONTAINMENT AIR SAMPLE RETURN ISOLATION VALVE TO MEET   |
| MAXIMUM INSERVICE TEST STROKE-TIME REQUIREMENTS                              |
|                                                                              |
| While performing quarterly valve stroke-time testing on Unit 3, a primary    |
| containment air sample return isolation valve exceeded its specified maximum |
| stroke-time limit.  The sample return line was isolated in accordance with   |
| Technical Specification 3.7.D for primary containment isolation valves, and  |
| this action satisfied the 4-hour limiting condition for operation action     |
| statement requirements.  The second in-line primary containment isolation    |
| system valve remains operable.                                               |
|                                                                              |
| The licensee stated that no other valves failed to meet the maximum          |
| stroke-time limits.  The licensee also stated that, during a test that was   |
| performed last month, the valve in question was identified as being in the   |
| 'Alert' time range for inservice test timing requirements and that it was    |
| being tested per the required increased testing frequency.  Corrective       |
| actions are being initiated, and troubleshooting activities are in           |
| progress.                                                                    |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
|                                                                              |
| *** UPDATE ON 04/23/99 AT 0443 FROM GADBOIS TO GOULD ***  RETRACTION         |
|                                                                              |
| UPON FURTHER REVIEW, IT WAS DETERMINED THAT THIS EVENT DID NOT CONSTITUTE A  |
| REPORTABLE CONDITION SINCE THE PENETRATION HAD AN OPERABLE REDUNDANT VALVE   |
| WHICH COULD HAVE ISOLATED THE CONTAINMENT PENETRATION.  THEREFORE, THE       |
| LICENSEE IS RETRACTING THIS EVENT NOTIFICATION.                              |
|                                                                              |
| THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR.  THE R3DO (LEACH)   |
| WAS NOTIFIED BY THE NRC OPERATIONS OFFICER.                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35612       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  MA DEPT OF PUBLIC HEALTH RCP         |NOTIFICATION DATE: 04/21/1999|
|LICENSEE:  AEA TECHNOLOGIES QSA, INC            |NOTIFICATION TIME: 15:00[EDT]|
|    CITY:  BURLINGTON               REGION:  1  |EVENT DATE:        04/21/1999|
|  COUNTY:                            STATE:  MA |EVENT TIME:        14:00[EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  04/23/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MOHAMED SHANBAKY     R1      |
|                                                |FREDERICK COMBS      NMSS    |
+------------------------------------------------+JOSEPH GIITTER       IRO     |
| NRC NOTIFIED BY:  KEN TRAEGDE                  |DONNA MARIE PEREZ    IP      |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |LEN WERT             R2      |
+------------------------------------------------+DALE POWERS          R4      |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|NOCM                     COMM ASST BRIEF        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - SHIPMENT OF 8 Ir-192 SOURCES (866 CURIES TOTAL) FROM BURLINGTON, MA,       |
| OVERDUE IN MEXICO -                                                          |
|                                                                              |
| AT 1500 EDT ON 04/21/99, KEN TRAEGDE OF THE MA DEPARTMENT OF PUBLIC HEALTH   |
| RADIATION CONTROL PROGRAM (RCP) LOCATED IN BOSTON, MA, REPORTED THAT ON      |
| 04/16/99, AEA TECHNOLOGY QSA, INC., LOCATED IN BURLINGTON, MA, SHIPPED A     |
| MODEL #855 SOURCE CHANGER LOADED WITH 8 Ir-192 SOURCES (TOTALING 866 CURIES) |
| VIA FEDERAL EXPRESS TO VICONT S.A. DE C.V. LOCATED IN TOLUCA, MEXICO.  THE   |
| UNDAMAGED PACKAGE HAD A TRANSPORT INDEX OF 1.4 (NORMAL READINGS OF 1.4 mR/HR |
| AT 1 METER AND 55 mR/HR AT THE SURFACE) AT THE TIME OF SHIPMENT.             |
|                                                                              |
| THE SHIPMENT WAS SCHEDULED TO ARRIVE IN MEXICO ON 04/17/99.  AS OF 1400 EDT  |
| ON 04/21/99, THE RECIPIENT (VICONT S.A. DE C.V.) HAD RECEIVED THE SHIPPING   |
| PAPERS BUT NOT THE CONTAINER.  THE SHIPPER AND FEDERAL EXPRESS HAVE LAUNCHED |
| A FULL SEARCH FOR THE PACKAGE.  THE FEDERAL EXPRESS HAZARDS MATERIAL         |
| INVESTIGATION TEAM HAS CONDUCTED A PHYSICAL SEARCH OF EXPRESS DEPOTS IN      |
| BOSTON, MEMPHIS, LOS ANGELES, AND MEXICO.                                    |
|                                                                              |
| THE LICENSE NUMBERS ARE:  SU-1485, 12-8361, 52-0243, 54-0237, AND 58-0242.   |
|                                                                              |
| THE NRC OPERATIONS OFFICER NOTIFIED THE DOT NATIONAL RESPONSE CENTER         |
| (GAUTHIER); REPORT NUMBER 481132.                                            |
|                                                                              |
| (CONTACT THE NRC OPERATIONS OFFICER FOR APPLICABLE TELEPHONE NUMBERS.)       |
|                                                                              |
| *********************************** UPDATE AT 1345 ON 04/22/99 BY JONES      |
| ***********************************                                          |
|                                                                              |
| The NRC entered the Monitoring Phase of Normal Mode at 1345 on 04/22/99.     |
| The NRC operations officer notified, the R1DO (Shanbaky), Region 1 (Miller), |
| IRO (Congel and Giitter), NMSS (Paperiello), RCT (Weinstein), PAO (Gagner),  |
| EDO's office (Charleen Raddatz), and Chairman's office (Holian).  The RCT    |
| notified  FEMA (Dan Rishe), DOE (Thomas Yates), EPA (Ms. Reddy), USDA (Bob   |
| Conley), HHS/CDC (James Raab), and DOT (Rick Boyle).                         |
|                                                                              |
| *********************************** UPDATE AT 1600 ON 04/22/99 BY JONES      |
| ***********************************                                          |
|                                                                              |
| A Commissioner's Assistants Briefing was conducted at 1600 on 04/22/99.  The |
| following notifications were made (* office did not participate):  IRO (Joe  |
| Giitter and Eric Weinstein), Chairman Jackson (Dan Gillen), Commissioner     |
| Dicus (Joel Lubenau), Commissioner Diaz (Patrick Castleman), Commissioner    |
| McGaffigan (Janet Schlueter), Commissioner Merrifield (JohnThoma), EDO (*),  |
| DEDE (*), NMSS (Don Cool and Carl Paperiello), NMSS EO (Fred Combs), R1DO    |
| (Mohamed Shanbaky), PAO (Joe Gilland), CAO (Thomas Madden), SECY (Andrew     |
| Bates), SP (Paul Lohaus), IP (Ron Hauber), Region 1 (Felicia Hinson and Jim  |
| Wiggins, etc), and Region 2 (Doug Collins, Chuck Hosey, and Dick Woodruff).  |
| The briefer was Fred Combs of NMSS.                                          |
|                                                                              |
| At 1610, the NRC operations officer played a tape of briefing for EDO (Dan   |
| Martin) and DEDE (Jocelyn Mitchell).                                         |
|                                                                              |
| ****************************** UPDATE AT 1230 ON 04/23/99 BY TROCINE AND     |
| JONES ******************************                                         |
|                                                                              |
| A conference call was conducted at 1230 on 04/23/99 to update the status of  |
| this event.  The following NRC offices participated (among others):  IRO     |
| (Himes), NMSS (Brach, Combs, and Cook), Region 1 (Loyd), Region 2 (Collins   |
| and Woodruff), Region 4 (Andrews), PAO (Hayden), IP (Lieberman), SP          |
| (Lohaus), and EDO (Raddatz).  In addition, the following agencies            |
| participated:  Department of Transportation (Rick Boyle), Massachusetts      |
| Department of Public Health RCP (Ken Traegdy), Federal Express (Scott Mugno, |
| Pat Oppenheimer, and Roy Parker), State of Tennessee (Alan Grewe), Tennessee |
| Division of Radiation Health (Eddy Nanney), AEA Technologies QSA, Inc. (Eric |
| Okvist), and Environmental Protection Agency located in Atlanta (Paul        |
| Wagner).                                                                     |
|                                                                              |
| During this conference call, representatives of Federal Express reported     |
| that they are confident that the shipment of 8 Ir-192 sources left Boston.   |
| They issued an 'all-points' search order, faxed a description to all         |
| 'logical' locations, and conducted repeat physical searches in Memphis,      |
| Boston, and Mexico, all without locating the shipment to date.  (The Los     |
| Angeles depot was not searched as had been reported on 04/21/99.)            |
| Massachusetts and Tennessee health authorities conducted radiological        |
| surveys in Boston and Memphis on 04/22/99 with negative results.             |
|                                                                              |
| Rick Boyle of the Department of Transportation notified the competent        |
| authority in Mexico, and Federal Express requested a detailed search of the  |
| Customs facilities in Mexico City.                                           |
|                                                                              |
| The next conference call is scheduled for 1230 EDT on Wednesday, 04/28/99.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35622       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 04/23/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 04:33[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        04/23/1999|
+------------------------------------------------+EVENT TIME:        02:14[CDT]|
| NRC NOTIFIED BY:  WELLER                       |LAST UPDATE DATE:  04/23/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI SYSTEM DECLARED INOPERABLE, AND PLANT ENTERED LCO ACTION STATEMENT.     |
|                                                                              |
| THE HPCI SYSTEM WAS DECLARED INOPERABLE FROM 0214 CDT TO 0220 CDT DUE TO     |
| MOISTURE IN THE TURBINE STEAM INLET LINE.  A 14-DAY LCO ACTION STATEMENT WAS |
| ENTERED, AND RCIC WAS VERIFIED OPERABLE.  HPCI TURBINE INLET HIGH DRAIN POT  |
| LEVEL ANNUNCIATION WAS RECEIVED  DUE TO STROKING MO-2036 (TURBINE STEAM      |
| SUPPLY VALVE) AS PART OF THE REACTOR SHUTDOWN PROCEDURE AT REACTOR PRESSURE  |
| OF 500 PSIG.  THE STEAM LINE MANUAL DRAIN VALVE WAS OPENED, AND THE          |
| ANNUNCIATOR CLEARED AT 0220 CDT.  HPCI WAS DECLARED OPERABLE AND IN STANDBY. |
| THE 14-DAY LCO ACTION STATEMENT WAS ALSO EXITED AT 0220 CDT.                 |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE.                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35623       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 04/23/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 10:16[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        04/23/1999|
+------------------------------------------------+EVENT TIME:        07:53[EDT]|
| NRC NOTIFIED BY:  GILLOW                       |LAST UPDATE DATE:  04/23/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     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       35       Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE PLANT HAD A REACTOR TRIP FROM 35% POWER ON A 2-OUT-OF-4 POWER RANGE HIGH |
| SIGNAL.                                                                      |
|                                                                              |
| THE REACTOR TRIP OCCURRED WHILE THE PLANT WAS COMING OUT OF A REFUELING      |
| OUTAGE AND THE I&C TECHNICIANS WERE WORKING ON THE NUCLEAR INSTRUMENTATION   |
| RACKS ADJUSTING POWER RANGE TRIP SETPOINTS.  CHANNEL 1 HAD JUST BEEN         |
| COMPLETED, AND CHANNEL 2 WAS IN PROGRESS WITH BOTH BISTABLES TRIPPED IN THE  |
| CHANNEL 2 PROTECTION RACKS.  AT THIS POINT, CONTROL ROOM TURNOVER HAD        |
| STARTED, AND THE TECHNICIANS HAD STOPPED WORK UNTIL TURNOVER WAS COMPLETE.   |
| UPON RESUMING WORK, THE TECHNICIANS INADVERTENTLY WENT TO NIS CHANNEL 3 AND  |
| PULLED INSTRUMENT POWER FUSES.  THE REACTOR TRIPPED ON  2 OUT OF 4 POWER     |
| RANGE HI LEVEL IMMEDIATELY UPON PULLING THE CHANNEL 3 FUSES.  ALL RODS FULLY |
| INSERTED, NO ECCS OCCURRED, AND NO SAFETY RELIEF VALVES LIFTED.  THE PLANT   |
| IS USING THE ATMOSPHERIC RELIEF VALVES AS THE HEAT SINK.  THE PLANT IS       |
| CURRENTLY IN MODE 3, Tavg IS 547F, AND RCS PRESSURE AT 2,235 PSIG.          |
|                                                                              |
| SINCE THE LICENSEE WAS COMING OUT OF A REFUELING OUTAGE, THE MAIN STEAM      |
| ISOLATION VALVES WERE CLOSED DUE TO LOW DECAY HEAT, AND THE MAIN STEAM       |
| GENERATOR ATMOSPHERIC VALVE ON EACH STEAM GENERATOR WAS USED TO MAINTAIN     |
| Tavg.                                                                        |
|                                                                              |
| THE INCIDENT WAS DUE TO PERSONNEL ERROR.                                     |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35624       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NATIONAL INSTITUTE OF HEALTH         |NOTIFICATION DATE: 04/23/1999|
|LICENSEE:  NATIONAL INSTITUTE OF HEALTH         |NOTIFICATION TIME: 13:38[EDT]|
|    CITY:  BETHERSDA                REGION:  1  |EVENT DATE:        04/21/1999|
|  COUNTY:  MONTGOMERY                STATE:  MD |EVENT TIME:        14:30[EDT]|
|LICENSE#:  19-00296-17           AGREEMENT:  Y  |LAST UPDATE DATE:  04/23/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MOHAMED SHANBAKY     R1      |
|                                                |FREDERICK COMBS      NMSS    |
+------------------------------------------------+JOSEPH GIITTER       IRO     |
| NRC NOTIFIED BY:  ROBERT ZOON                  |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AN IRRADIATOR FAILED TO PROPERLY RETURN THE SOURCE TO THE FULLY  SHIELDED    |
| POSITION.                                                                    |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "This is a report in accordance with condition 17.E. of license 19-00296-17  |
| which requires that with respect to each J. L. Shepherd and Associates Mark  |
| 1 Cesium-137 Irradiator, we ' ... notify the Commission by telephone ... if  |
| ... any malfunction of the irradiator is detected.                           |
|                                                                              |
| "At approximately 2:30 p.m. April 21, 1999, a health physicist (HP) in the   |
| Radiation Safety Branch was continuing a quarterly inspection and leak test  |
| procedure which he had initiated on April 19, 1999.  During this follow-up   |
| visit, he became aware of an apparent problem with a J. L. Shepherd Mark I   |
| Cesium-137 irradiator, which is located in Building 37, Room B440.  This     |
| self-contained self-shielded irradiator contains approximately 3,850 Ci of   |
| Cs-137.                                                                      |
|                                                                              |
| "The [HP] reported the results of his investigation to me at 9:15 a.m. this  |
| morning.  The problem was reported to the HP on April 21 by a designated     |
| user who explained that the source failed on at least one occasion to return |
| to the fully shielded position following an irradiation procedure.  The door |
| interlock functioned as designed, which prevented the door from being        |
| opened.  Thus, this situation resulted in NO safety problem or radiation     |
| exposure.                                                                    |
|                                                                              |
| "The HP, continuing his investigation, was able to duplicate a similar       |
| problem one additional time during the inspection.  However, numerous        |
| repeated attempts to duplicate the problem did not result in a failure of    |
| the irradiator to properly stow the source.  The HP did not, therefore,      |
| judge the irradiator to have malfunctioned.                                  |
|                                                                              |
| "Following the HP's discussion with me this morning, it was my judgement     |
| that the problem observed could be interpreted as a malfunction of the       |
| irradiator.  Therefore, effective this morning, I directed the irradiator    |
| custodian to remove this irradiator from service and to contact J. L.        |
| Shepherd for maintenance to correct this problem.  At that time, I also      |
| elected to report this apparent malfunction directly to you [Judith Joustra, |
| Chief, Nuclear Materials Safety Branch, Region 1].  Upon your advice, I am   |
| simultaneously reporting this finding to the NRC Operations Center.          |
|                                                                              |
| "Upon receipt of the report of maintenance from the J. L. Shepherd service   |
| representative, I will forward you the explanation for the irradiator's      |
| failure to operate."                                                         |
|                                                                              |
| (Call the NRC operations officer for a site contact telephone number.)       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35625       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 04/23/1999|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 16:42[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/23/1999|
+------------------------------------------------+EVENT TIME:        16:00[EDT]|
| NRC NOTIFIED BY:  S. SAUER                     |LAST UPDATE DATE:  04/23/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     R1      |
|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 DISCOVERED AT POSITIVE PRESSURE TO THE OUTSIDE.           |
|                                                                              |
| The licensee determined at 1600 on 04/23/99 that this report met the         |
| criteria for reporting under 10CFR50.72 as a 1-hour report.                  |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On 04/13/99 at 2135, the Unit 1 auxiliary building was found to be at a     |
| +0.03 inches of water with respect to the outdoors.  The Updated Final       |
| Safety Analysis Report (UFSAR) states that the auxiliary building is         |
| designed to be at a slight negative pressure continuously with respect to    |
| the outdoors, to satisfy the criterion for preventing the uncontrolled       |
| release of radioactivity.  Subsequent investigation found that the #12       |
| auxiliary building exhaust fan was rotating backwards.  The fan had been     |
| returned to service at 1337 on 04/13/99, the fan was removed from service at |
| 2216.  Maintenance inspections had been performed earlier that day that      |
| required the motor leads to be disconnected.  The apparent cause is miss     |
| wiring of the motor by the maintenance technician.  The fan was reworked and |
| returned to service at 1110 on 04/14/99.  Tech Spec 3.7.7.1 was in effect    |
| for the duration."                                                           |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35627       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 04/24/1999|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 05:09[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        04/24/1999|
+------------------------------------------------+EVENT TIME:        04:19[EDT]|
| NRC NOTIFIED BY:  BRIAN WEAVER                 |LAST UPDATE DATE:  04/24/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     R1      |
|10 CFR SECTION:                                 |WILLIAM BATEMAN      NRR     |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |JOSEPH GIITTER       IRO     |
|ACCS 50.72(b)(1)(iv)     ECCS INJECTION         |                             |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR SCRAM DUE TO UNKNOWN ELECTRICAL TRANSIENT                            |
|                                                                              |
| The reactor scrammed due to an unknown electrical transient.  All control    |
| rods fully inserted into the core.  Both electric-driven reactor feedwater   |
| pumps tripped, all three condensate booster pumps tripped, and the           |
| recirculation pumps tripped.  The plant is in natural circulation with high  |
| pressure core spray (HPCS) system injecting and maintaining reactor vessel   |
| water level between 160 to 200 inches.  (Normal reactor vessel water level   |
| is 184 inches, and the top of the active fuel is -18 inches.)  Reactor core  |
| isolation cooling (RCIC) and HPCS received automatic initiation signals on   |
| Level 2, and the Division 3 diesel automatically started but did not load.   |
| The RCIC pump failed to come up to speed and has been tripped.  The main     |
| steam isolation valves are open, and reactor vessel pressure is being        |
| maintained at 600 to 700 psig.  Uninterruptible power supply (UPS) "3B"      |
| tripped and has a blown fuse which prevents resetting of the inboard         |
| containment isolation valves.  Both Containment Monitoring System(CMS)       |
| cabinets 10A and 10B are isolated (leak detection for particulate and        |
| gaseous) causing entry into Technical Specification 3.0.3.  Due to UPS "3B"  |
| being tripped, the licensee has a one-half isolation signal to the main      |
| steam isolation valves.  UPS "3B" provides logic to the scram system, etc.   |
| (UPS "3B" is essentially a major logic power supply for UPS.)                |
|                                                                              |
| The electrical transient (not sure if the transient was caused from offsite  |
| site power loss) caused a partial loss of lighting in the control room, a    |
| complete loss of lighting to the turbine building (was reported), and a loss |
| of site perimeter lighting for a very short period of time.  All UPS went to |
| a battery source of power for a short period of time and then transferred    |
| back to normal power source (normally happens on a big electrical            |
| transient).  All electrical in-house buses powered up, and the plant is      |
| stable.  A condensate booster pump has been reestablished, and the licensee  |
| is starting to investigate what caused the electrical transient, RCIC not    |
| coming up to speed (places them in Tech Spec 3.7.4), and what caused the     |
| fuse to blow to UPS "3B."                                                    |
|                                                                              |
| The licensee had not, at the time of this call, checked with Unit 1 to see   |
| if it had experienced a power loss for a short period of time.               |
|                                                                              |
| The NRC resident inspector will be notified of this event by the licensee.   |
|                                                                              |
| ***UPDATE AT 0751 EDT FROM ROY GREEN TAKEN BY MACKINNON***                   |
|                                                                              |
| The licensee updated this event to add the 4-hour notifications under 10 CFR |
| 50.72 (b)(2) for a reactor protection system actuation, engineered safety    |
| feature (ESF) actuations, and accident mitigation.  The 4-hour notifications |
| were required for the reactor scram and the following ESF actuations:        |
| reactor water cleanup system isolation, standby gas initiation, control room |
| special filter train initiation, reactor vessel water Level 2 containment    |
| isolations, and Division 3 (HPCS) automatic start on HPCS initiation. The    |
| third 4-hour notification was required for accident mitigation due to single |
| train RCIC failure upon initiation.                                          |
|                                                                              |
| Plant Status:                                                                |
|                                                                              |
| The scram has been reset, normal cooldown is in progress via the turbine     |
| bypass valves, reactor vessel water level is being maintained in its normal  |
| band with normal feedwater system, and UPS-3B remains de-energized           |
| preventing containment isolation recovery.  Troubleshooting is in progress   |
| on UPS-3B and RCIC.  (The region of instability on the power to flow map was |
| not entered.)                                                                |
|                                                                              |
| The licensee plans to place the unit in a Cold Shutdown condition on natural |
| circulation.                                                                 |
|                                                                              |
| The NRC resident inspector was notified of this update by the licensee.  The |
| R1DO ( Mohamed Shanbaky) was notified by the NRC operations officer.         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35628       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  GAMMA-METRICS                        |NOTIFICATION DATE: 04/23/1999|
|LICENSEE:  GAMMA-METRICS                        |NOTIFICATION TIME: 18:00[EDT]|
|    CITY:  SAN DIEGO                REGION:  4  |EVENT DATE:        04/23/1999|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  04/24/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MOHAMED SHANBAKY     R1      |
|                                                |LEN WERT             R2      |
+------------------------------------------------+MELVYN LEACH         R3      |
| NRC NOTIFIED BY:  ROBERT BARNES                |VERN HODGE(FAX)      NRR     |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INFORMATION ON A DEVIATION THAT DOES NOT REACH THE LEVEL OF A PART 21        |
| REPORT                                                                       |
|                                                                              |
| There was an incorrect resistor shipped on log amplifier printed circuit     |
| assemblies.  The worst case environmental temperature deviation would cause  |
| a maximum deviation of 6% (equivalent full-scale) error in the indicating    |
| region from 3 X 10-3% to 50% power.  This would not compromise the ability   |
| to monitor safe shutdown reactor power level adequately during and after a   |
| design basis event.                                                          |
|                                                                              |
| The following text is a portion of a facsimile received from GAMMA-METRICS:  |
|                                                                              |
| "Our lot control capability allowed us to determine that nineteen of the     |
| incorrect resistors were shipped from GAMMA-METRICS to our customers. ... We |
| are recalling all nineteen defective resistors or the printed circuit        |
| assemblies.  We will replace the resistors with the correct component and    |
| re-certify the repair at no charge to any of the listed customers."          |
|                                                                              |
| The following is a list of the facilities affected:                          |
|                                                                              |
| 1.  Georgia Power, Vogtle 1 and 2 - 9 assemblies (replaced in March 1999)    |
| 2.  Duke Energy, Catawba - 1 assembly                                        |
| 3.  AEP DC Cook - 2 assemblies (not installed)                               |
| 4.  Ontario Hydro, Pickering - 1 assembly (not installed)                    |
| 5.  Maine Yankee - 4 assemblies (not installed and plant shutdown for        |
| decommissioning)                                                             |
| 6.  Penn State University - 2 assemblies (not installed)                     |
|                                                                              |
| There were letters sent to the affected customers.                           |
|                                                                              |
| (Call the NRC operations officer for a contact telephone number.)            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35629       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 04/24/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 13:09[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        04/24/1999|
+------------------------------------------------+EVENT TIME:             [CDT]|
| NRC NOTIFIED BY:  KEVIN PETERSON               |LAST UPDATE DATE:  04/24/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| REACTOR WATER LEVEL HIGH ENOUGH TO ENTER THE MAIN STEAM LINES  (Refer to     |
| event numbers 35617 and 35618 for event-related information.)                |
|                                                                              |
| During an engineering evaluation of the reactor scram that occurred on       |
| 04/22/99, it was determined that reactor water level entered the main steam  |
| lines.  This potentially made reactor core isolation cooling and high        |
| pressure coolant injection inoperable.  The cause of the high water level    |
| condition is under investigation.                                            |
|                                                                              |
| The licensee notified the NRC Resident Inspector and intends to notify state |
| and local government agencies.                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35630       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 04/24/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 15:28[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        04/24/1999|
+------------------------------------------------+EVENT TIME:             [CDT]|
| NRC NOTIFIED BY:  JIM SCHOTTEL                 |LAST UPDATE DATE:  04/24/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SAFETY PARAMETER DISPLAY SYSTEM (SPDS) OUT OF SERVICE DUE TO MAINTENANCE.    |
|                                                                              |
| Planned maintenance on an uninterruptible power supply bus (1B) for the      |
| process computer will disable some points on the SPDS for 48 hours.          |
| Operators are taking compensatory measures for monitoring parameters.        |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35631       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD                REGION:  3  |NOTIFICATION DATE: 04/24/1999|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 22:15[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/24/1999|
+------------------------------------------------+EVENT TIME:        19:36[CDT]|
| NRC NOTIFIED BY:  MARK ANDREWS                 |LAST UPDATE DATE:  04/24/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MELVYN LEACH         R3      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH STEAM GENERATOR LEVEL ESF ACTUATION                                     |
|                                                                              |
| During cooldown, after performing a plant shutdown for a refueling outage,   |
| narrow range level was noted to be increasing in the '2A' and '2C' steam     |
| generators.  The feedwater isolation valves were checked closed, and         |
| additional manual isolation valves were closed.  Steam generator blowdown    |
| was in the process of being put in service when level reached the P14        |
| setpoint which caused an engineered safety features actuation (includes main |
| feedwater pump trip and feedwater isolation signal).                         |
|                                                                              |
| Further investigation found auxiliary feedwater valves open that together    |
| with the pressure head from the water level in the condensate tank was       |
| sufficient to feed the steam generators.                                     |
|                                                                              |
| Steam generator level was restored once blowdown was established.            |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35632       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 04/26/1999|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 01:41[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        04/26/1999|
+------------------------------------------------+EVENT TIME:        00:01[EDT]|
| NRC NOTIFIED BY:  FERNSLER                     |LAST UPDATE DATE:  04/26/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     R1      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       2        Startup          |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 2 WAS MANUALLY SCRAMMED FROM 2% POWER TO PERMIT ENTRY INTO THE DRYWELL  |
| FOR REPAIR WORK.                                                             |
|                                                                              |
| THE UNIT WAS MANUALLY SHUTDOWN TO PERMIT ENTRY INTO CONTAINMENT TO PERFORM   |
| REPAIRS TO THE TRANSVERSING INCORE PROBE(TIP) CHANNEL TUBING.  PRIOR TO      |
| SHUTDOWN THE UNIT WAS IN THE PROCESS OF RESTARTING FOLLOWING THE 9TH         |
| REFUELING OUTAGE.  DURING POST MAINTENANCE TESTING, A RESTRICTION WAS        |
| DISCOVERED IN THE TUBING OF THE "C" TIP MECHANISM.  THIS PREVENTED INSERTION |
| OF ITS DETECTOR AND CALIBRATION OF ITS ASSOCIATED LPRM.  IN ORDER TO PERFORM |
| REPAIRS, THE REACTOR HAD TO BE SHUTDOWN FOR DRYWELL ENTRY.  FOLLOWING        |
| SHUTDOWN REACTOR WATER LEVEL REMAINED ESSENTIALLY UNCHANGED AT 35.7" AS      |
| RECORDED ON THE NARROW RANGE INSTRUMENTATION.  ALL RODS FULLY INSERTED, NO   |
| ECCS INITIATIONS OR DIESEL STARTS OCCURRED AND NO SAFETY RELIEF VALVES       |
| LIFTED.  THIS EVENT IS NOT REPORTABLE AS A RPS ACTUATION SINCE IT IS         |
| PROCEDURALLY RECOGNIZED AS PRE-PLANNED.  HEAT SINK IS THE SHUTDOWN COOLING   |
| TO THE SUPPRESSION POOL.  THEY WILL CONTINUE COOLDOWN TO MODE 4.             |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+