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Event Notification Report for April 27, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/26/1999 - 04/27/1999

                              ** EVENT NUMBERS **

35601  35612  35630  35632  35633  35634  35635  35636  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35601       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 04/18/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 01:41[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        04/17/1999|
+------------------------------------------------+EVENT TIME:        22:14[EDT]|
| NRC NOTIFIED BY:  DON ROLAND                   |LAST UPDATE DATE:  04/26/1999|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAN HOLODY           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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 1 HAD LESS THAN THREE OPERABLE DIESEL GENERATORS FOR A SHORT PERIOD OF  |
| TIME.                                                                        |
|                                                                              |
| During restoration from loss of coolant accident/loss of offsite power       |
| (LOCA/LOOP) Division II testing on Unit 2, which is shutdown, operators      |
| inadvertently placed the 'D' Diesel Generator Synchronization Auto Control   |
| Select Switch to Bypass with the 'B' Diesel Generator already in Bypass per  |
| plant procedures.  This action requires the diesel be declared inoperable.   |
| The action was immediately identified, and the switch on the 'D' Diesel was  |
| returned to Normal.  The total time that two diesel generators were          |
| inoperable was less than 1 minute.  This left Unit 1 with only the 'A' and   |
| 'C' Diesel Generators operable.                                              |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
|                                                                              |
| ******************** UPDATE AT 1720 ON 04/26/99 FROM JEFF HELSEL TO TROCINE  |
| ********************                                                         |
|                                                                              |
| The licensee is retracting this event notification.                          |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Diesel Generator 'D' remained operable and fully capable of performing its  |
| intended safety functions on 04/17/99 at approximately 2214 when the 43SYN   |
| switch was placed in bypass.  This occurred during the performance of Unit 2 |
| Division II LOCA/LOOP testing.  At the time of this condition, the diesel    |
| was running in the emergency (isochronous) mode of operation supplying the   |
| 2D [emergency safeguards system (ESS)] bus.  Placing the Synchronization     |
| Auto Control Select Switch (43SYN) to bypass enables manual control of both  |
| the speed and voltage setpoints to enable paralleling back to offsite power. |
| It does not place the diesel in the droop mode.  With the 43SYN in normal, a |
| fixed resistance for frequency and a fixed motor-operated potentiometer      |
| resistance for voltage is input into the circuitry.  Placing the switch in   |
| bypass maintains these same resistance values and enables circuits for       |
| manually adjusting frequency and voltage.  As long as manipulation of the    |
| controlling switches does not occur, the values remain at their initial      |
| setting.  Post-event interviews with the [plant control operator] in control |
| revealed [that] no adjustments were made.  That is to say that frequency     |
| will remain at 60 Hz and will return to 60 Hz following picking up or        |
| shedding of loads.  The same is true of voltage.  Initial voltage was 4,250  |
| when the switch was in normal and remained at 4,250 following placing in     |
| bypass.  Voltage will return to the initial value following load pickup or   |
| shedding.  The transient recovery time for both frequency and voltage is     |
| expected to be identical for both bypass and normal positions under these    |
| specific conditions.  This conclusion of operability is based on a detailed  |
| review of system circuitry, system design features and a review of 2D ESS    |
| bus voltage data at the time of the occurrence."                             |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R1DO (Anderson).                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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:  04/26/1999|
|  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 Massachusetts Department of      |
| Public Health Radiation Control Program (RCP) located in Boston,             |
| Massachusetts, reported that on 04/16/99, AEA Technology QSA, Inc., located  |
| in Burlington, Massachusetts, shipped a Model-855 source changer loaded with |
| eight Iridium-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/hour at 1 meter and 55     |
| mR/hour 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 Hazardous 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 Department of Transportation via the |
| 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), OPA (Gagner),  |
| EDO's office (Charleen Raddatz), and Chairman's office (Holian).  The RCT    |
| notified the Federal Emergency Management Agency (Dan Rishe), Department of  |
| Energy (Thomas Yates), Environmental Protection Agency (Ms. Reddy),          |
| Department of Agriculture (Bob Conley), Department of Health and Human       |
| Services (James Raab), and Department of Transportation (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 (*Dan |
| Martin), DEDE (*Jocelyn Mitchell), NMSS (Don Cool and Carl Paperiello), NMSS |
| EO (Fred Combs), R1DO (Mohamed Shanbaky), OPA (Joe Gilland), CAO (Thomas     |
| Madden), SECY (Andrew Bates), OSP (Paul Lohaus), OIP (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 (Lloyd), Region 2 (Collins  |
| and Woodruff), Region 4 (Andrews), OPA (Hayden), OIP (Lieberman), OSP        |
| (Lohaus), and EDO (Raddatz).  In addition, the following agencies            |
| participated:  Department of Transportation (Rick Boyle), Massachusetts      |
| Department of Public Health RCP (Ken Traegde), Federal Express (Scott Mugno, |
| Pat Oppenheimer, and Roy Parker), State of Tennessee (Alan Grewe), Tennessee |
| Division of Radiation Health (Eddy Nanney), AEA Technology 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 eight Iridium-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.   |
|                                                                              |
| ************************* UPDATE AT 1333 ON 04/26/99 FROM TRAEGDE TO TROCINE |
| *************************                                                    |
|                                                                              |
| At 0619 EDT on 04/26/99, Federal Express confirmed that the serial number on |
| a Model-855, Type-B package found at the Stansted Airport (located outside   |
| of London, England) matched the serial number for the missing package        |
| containing the eight Iridium-192 sources.  The Massachusetts Department of   |
| Public Health RCP was informed of this discovery by AEA Technology QSA,      |
| Inc., at 0933 EDT on 04/26/99.  The package was reported to be intact and    |
| undisturbed.  The carrier (Federal Express) contacted the shipper (AEA       |
| Technology QSA, Inc.), and the shipper requested that the package be         |
| forwarded to its intended destination.  Accordingly, the package will be     |
| shipped from Stansted Airport to Toluca, Mexico, via Memphis, Tennessee.     |
| Federal Express informed the Massachusetts Department of Public Health RCP   |
| that the package is expected to arrive in Memphis, Tennessee, by tomorrow    |
| morning (04/27/99).                                                          |
|                                                                              |
| The Massachusetts Department of Public Health RCP notified NRC Region 1      |
| (Duncan White).  The NRC Operations Officer notified the R1DO (Anderson);    |
| R2DO (Wert); R4DO (Graves); NMSS (Combs); IRO (Giitter, Miller, and Congel); |
| RCT (Bailey).                                                                |
|                                                                              |
| *********************************** UPDATE AT 1600 ON 04/26/99 BY TROCINE    |
| ***********************************                                          |
|                                                                              |
| A conference call was conducted at 1600 on 04/26/99 to update the status of  |
| this event.  The following NRC offices participated (*office did not         |
| participate):  IRO (Giitter), RCT (Bailey), NMSS (Brach and Cool), Region 1  |
| (Kinneman), Region 2 (Hosey), Region 4 (*Graves), Region 1 Public Affairs    |
| (*Screnci and *Sheehan), HQ OPA (Beecher), OIP (Lieberman), OSP (Bolling and |
| Lohaus), and EDO (Raddatz).  In addition, the following agencies             |
| participated:  Massachusetts Department of Public Health RCP (Ken Traegde),  |
| State of Tennessee (Alan Grewe and Mike Mobley), and Tennessee Division of   |
| Radiation Health (Eddy Nanney).                                              |
|                                                                              |
| Based upon the information discussed during this conference call (reference  |
| the 1333 04/26/99 update above), the NRC exited the Monitoring Phase of      |
| Normal Mode at 1615 on 04/26/99.                                             |
|                                                                              |
| The NRC operations officer notified the IRO (Giitter, Miller, and Congel);   |
| RCT (Bailey); NMSS EO (Cool); NMSS (Brach); Region 1 (Kinneman); Region 2    |
| (Hosey); R1DO (Anderson); R2DO (Wert); R4DO (Graves); OPA (Beecher); OIP     |
| (Lieberman); OSP (Bolling and Lohaus); and EDO (Raddatz).  The RCT notified  |
| the Federal Emergency Management Agency (Dan Rishe), Department of Energy    |
| (Thomas Yates), Environmental Protection Agency (Ms. Reddy), Department of   |
| Agriculture (Bob Conley), Department of Health and Human Services (James     |
| Raab), and Department of Transportation (Rick Boyle).                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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:        14:30[CDT]|
| NRC NOTIFIED BY:  JIM SCHOTTEL                 |LAST UPDATE DATE:  04/26/1999|
|  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 uninterruptible power supply (UPS) 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.                            |
|                                                                              |
| ******************** UPDATE AT 1910 ON 04/26/99 FROM RICH CHEAR TO TROCINE   |
| ********************                                                         |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On 04/24/99, Clinton Power Station reported that plant [SPDS] was not       |
| available during the planned UPS 1B bus outage.  During this time, the       |
| control room operators monitored other information sources for the           |
| information unavailable on SPDS."                                            |
|                                                                              |
| "On 04/26/99, the UPS 1B bus [was] returned to service, and the SPDS [was]   |
| restored at 1720 [CDT].  The SPDS is now available and operational."         |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R3DO (Madera).                                          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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 ALLOW     |
| PERFORMANCE OF REPAIRS TO THE TRAVERSING INCORE PROBE (TIP) CHANNEL TUBING.  |
| PRIOR TO SHUTDOWN, THE UNIT WAS IN THE PROCESS OF RESTARTING FOLLOWING THE   |
| NINTH 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 LOCAL POWER RANGE MONITOR  |
| (LPRM).  IN ORDER TO PERFORM REPAIRS, THE REACTOR HAD TO BE SHUT DOWN FOR    |
| DRYWELL ENTRY.  FOLLOWING THE 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 AN RPS ACTUATION SINCE IT IS PROCEDURALLY RECOGNIZED AS        |
| PRE-PLANNED.  THE HEAT SINK IS THE SHUTDOWN COOLING TO THE SUPPRESSION POOL. |
| THE LICENSEE PLANS TO CONTINUE COOLING THE UNIT DOWN TO MODE 4.              |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35633       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  SUNOCO INC.                          |NOTIFICATION DATE: 04/26/1999|
|LICENSEE:  SUNOCO INC.                          |NOTIFICATION TIME: 08:48[EDT]|
|    CITY:  TULSA                    REGION:  4  |EVENT DATE:        04/25/1999|
|  COUNTY:                            STATE:  OK |EVENT TIME:        18:36[CDT]|
|LICENSE#:  35-01755-02           AGREEMENT:  N  |LAST UPDATE DATE:  04/26/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAVID GRAVES         R4      |
|                                                |FREDERICK COMBS      NMSS    |
+------------------------------------------------+JOSEPH GIITTER       IRO     |
| NRC NOTIFIED BY:  MEFFORD                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE SUNOCO FACILITY REPORTED AN EXPLOSION WHICH OCCURRED IN THEIR COKER      |
| UNIT.                                                                        |
|                                                                              |
| IN THE AREA WHERE THE EXPLOSION OCCURRED, THERE ARE FOUR 1,500 mCi CS-137    |
| SOURCES; TWO EACH MOUNTED ON THE NORTH SIDE OF THE TWO 16-FOOT DRUMS.  THE   |
| EXPLOSION OCCURRED APPROXIMATELY 50 FEET FROM THE SOUTH SIDE OF THE DRUMS.   |
| THE SOURCES WERE SHIELDED BY THE COKE DRUMS, AND IT WAS VERIFIED THAT THEY   |
| ARE STILL PHYSICALLY ATTACHED TO THE UNDAMAGED DRUMS AND DO NOT APPEAR TO BE |
| DAMAGED THEMSELVES.  THE LICENSEE PLANS TO CONDUCT WIPE TESTS TODAY AND LOCK |
| THE SHUTTERS.  THE CAUSE OF THE EXPLOSION IS UNKNOWN AND BEING INVESTIGATED. |
| THE DAMAGE, WHICH CAN BE OBSERVED SOUTH OF THE DRUMS, CONSISTS OF ONLY       |
| INSULATION DAMAGE.                                                           |
|                                                                              |
| (CALL THE NRC OPERATIONS OFFICER FOR CONTACT TELEPHONE NUMBERS.)             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35634       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 04/26/1999|
|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 11:13[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        04/26/1999|
+------------------------------------------------+EVENT TIME:        08:37[EDT]|
| NRC NOTIFIED BY:  HILBERT-SEMMES               |LAST UPDATE DATE:  04/26/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LEN WERT             R2      |
|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        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE PLANT RECEIVED A TRAIN "B" HIGH CONSEQUENCE-LIMITING SAFEGUARDS (CLS)    |
| SIGNAL.                                                                      |
|                                                                              |
| THIS OCCURRED WHEN AN ELECTRICIAN LIFTED A LEAD WHILE REPLACING RELAY        |
| "2-CLS-RLY-1B1" IN THE "B" TRAIN HIGH CLS SYSTEM.  ONE CONTAINMENT TRIP      |
| VALVE FOR THE CONTAINMENT PARTICULATE AND GAS RADIATION MONITORS             |
| REPOSITIONED (CLOSED), AND THE PARTICULATE AND GAS RADIATION MONITOR PUMP    |
| DE-ENERGIZED.   A SAFETY INJECTION SIGNAL WAS NOT RECEIVED AS IT WAS         |
| PROPERLY DEFEATED IN ACCORDANCE WITH STATION PROCEDURES.  THE ELECTRICIANS   |
| VERIFIED THAT THE HIGH CLS SYSTEM WAS DE-ENERGIZED AS THEY WOULD EXPECT      |
| PRIOR TO PERFORMING WORK TO PREVENT A SPURIOUS ACTUATION.  THE LICENSEE IS   |
| INVESTIGATING THE CAUSE AND THE REQUIRED CORRECTIVE ACTIONS.  THE HIGH CLS   |
| SIGNAL WAS RESET SINCE THE 2/4 CONTAINMENT PRESSURE < 14.2 PSIA MATRIX WAS   |
| MET DUE TO THE ACCURACY OF THE GAUGES.  THE TRIP VALVE WAS PLACED IN THE     |
| PRE-EVENT CONDITION (OPEN), AND THE RADIATION MONITOR PUMP WAS RE-ENERGIZED  |
| AND RESTARTED.  CORE OFF LOAD WAS NOT IN PROGRESS AT THE TIME OF THIS        |
| EVENT.                                                                       |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35635       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS           REGION:  1  |NOTIFICATION DATE: 04/26/1999|
|    UNIT:  [1] [2] []                STATE:  MD |NOTIFICATION TIME: 16:08[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        03/28/1999|
+------------------------------------------------+EVENT TIME:             [EDT]|
| NRC NOTIFIED BY:  L. SMIALEK/D. BAUDER         |LAST UPDATE DATE:  04/26/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLIFFORD ANDERSON    R1      |
|10 CFR SECTION:                                 |FREDERICK COMBS      NMSS    |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF FOUR CESIUM-137 SOURCES (288 MICROCURIES TOTAL) (30-day report)      |
|                                                                              |
| Four Cs-137 sources were discovered to be missing during the performance of  |
| a quarterly inventory of licensed material on 03/28/99.  The sources were    |
| located in a source lockup area that was under the control of radiation      |
| safety, and they were present during the previous quarterly inventory.       |
| There was a long-term (several-year) cleanup project ongoing at the time,    |
| and numerous sources were scheduled for disposition into waste burial.  The  |
| licensee identified 76 sources in the newest bag but could not account for 4 |
| sources (according to the inventory).                                        |
|                                                                              |
| At this time, the licensee believes that the sources may have exited the     |
| radiation controlled area as dry active waste as a result of nuclear         |
| housekeeping.    The current dose rate for each source was calculated to be  |
| less than 0.3 mR/hour at a distance of 1' (unshielded).                      |
|                                                                              |
| The sources were manufactured by Victoreen and were labeled as capsules.     |
| Each capsule had dimensions of approximately 1/4" by 1/2" in diameter with a |
| small activity chamber at the bottom of the shaft.  This was imbedded into a |
| 1/2" to 1" plastic wafer with a diameter of 3".  The sources were described  |
| as being too small to have a number on them; so they were labeled with magic |
| marker across the side of the plastic disc.                                  |
|                                                                              |
| The missing sources were used as keep-alive sources for the radiation        |
| monitoring system (RMS).  In that configuration, sources were designed to    |
| develop a signal of 20 mR/hour for radiation monitors so that it is known    |
| that the RMS is constantly working.  The sources in question were installed  |
| in the Unit 1 main steam RMS in 1985.  (At that time, the sources were       |
| reported to be 100 mCi each, and it was reported that each of the missing    |
| sources has since decayed to 72 mCi.)  The main steam RMS was replaced in    |
| 1997.  Two of the missing sources were removed on 03/21/97, and two were     |
| removed on 04/25/97.  The sources were then labeled for disposition.         |
|                                                                              |
| Considered individually, the activity of each source is less than the        |
| reportable limits specified in 10 CFR Part 20, Appendix C.  However,         |
| considered in the aggregate, the activity for the total loss of material     |
| (288 mCi) exceeds the reportable quantity of 100 mCi for Cesium-137, which   |
| is 10 times the value listed in Appendix C (10 mCi) per source.  The missing |
| sources were reportedly located in one bag, so the licensee is considering   |
| the missing sources as a single entity.                                      |
|                                                                              |
| After identification of the missing sources on 03/28/99, the licensee        |
| notified the NRC resident inspector and NRC Region 1 (Ronald Nimitz).  The   |
| licensee also notified the NRC resident inspector of this event notification |
| to the NRC Operations Center.  In addition, the licensee plans to submit a   |
| licensee event report within 30 days.                                        |
|                                                                              |
| (Call the NRC operations officer for licensee contact telephone numbers.)    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35636       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 04/26/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 23:47[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        04/26/1999|
+------------------------------------------------+EVENT TIME:        23:15[EDT]|
| NRC NOTIFIED BY:  GREG SOSSON                  |LAST UPDATE DATE:  04/26/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CLIFFORD ANDERSON    R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF TWO LOCAL POWER RANGE MONITORS INDICATING INCONSISTENTLY WITH   |
| THE REMAINING LOCAL POWER RANGE MONITORS                                     |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Upon review of local power range monitor (LPRM) data for Unit 1, [two]      |
| LPRMs were determined be indicating inconsistently with the remaining LPRMs. |
| The cause is believed to be reversed cable inputs to the LPRM drawer.  The   |
| problem is believed to be under-vessel.                                      |
|                                                                              |
| "As a result of this condition, the 'B' and 'D' [average power range         |
| monitors (APRMs)] and both rod block monitor [(RBM)] channels were declared  |
| inoperable at 2315 [on 04/26/99].  This condition has existed since the      |
| previous refueling outage [which was exited] in June [of] 1998.              |
|                                                                              |
| "The suspect LPRMs are being bypassed which will restore the APRMs and RBMs  |
| to an OPERABLE status.                                                       |
|                                                                              |
| "Generic investigations are in progress; however, initial review of          |
| operating data indicates normal operation of [the] remaining LPRMs.  This    |
| investigation will analyze any impact on thermal limits and fuel             |
| performance."                                                                |
|                                                                              |
| The licensee stated that the RBMs are not required for operability at this   |
| time.  However, the unit is currently in a 12-hour limiting condition for    |
| operation (LCO) which requires insertion of a half scram for the two         |
| inoperable APRMs.  This LCO will be exited when the LPRMs are bypassed.  The |
| licensee does not anticipate any problems meeting this LCO action statement. |
| The licensee also stated that with the exceptions noted above, all systems   |
| functioned as designed and there was nothing unusual or misunderstood.       |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+