The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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.                     |
+------------------------------------------------------------------------------+


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