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Event Notification Report for January 24, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/21/2000 - 01/24/2000

                              ** EVENT NUMBERS **

36610  36611  36612  36613  36614  36615  36616  36617  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36610       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 01/21/2000|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 04:21[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        01/21/2000|
+------------------------------------------------+EVENT TIME:        02:39[CST]|
| NRC NOTIFIED BY:  JOHN SELL                    |LAST UPDATE DATE:  01/21/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID HILLS          R3      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       40       Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 1 MANUALLY TRIPPED FROM 40% POWER DUE TO A DECREASING FOREBAY LEVEL     |
|                                                                              |
| "UNIT 1 WAS MANUALLY TRIPPED FROM 40% POWER AFTER AN ANTICIPATORY POWER      |
| REDUCTION AT 0239CST DUE TO DECREASING LEVEL IN THE CIRC. WATER INLET        |
| FOREBAY.  DECREASING LEVEL WAS APPARENTLY DUE TO ICING OF THE INTAKE         |
| STRUCTURE.  UNIT 1 CIRC. WATER SYSTEM HAS BEEN SECURED AND FOREBAY LEVEL HAS |
| INCREASED.  THE UNIT 1 CIRC. WATER SYSTEM WAS SECURED TO MAINTAIN            |
| OPERABILITY OF THE SERVICE WATER SYSTEM.  UNIT 2 REMAINS AT 100% POWER AND   |
| IS STABLE."                                                                  |
|                                                                              |
| FOREBAY LEVEL HAD DECREASED TO -11 FT FROM THE NORMAL OPERATING -8 FT.  THE  |
| -11 FT CORRESPONDS TO THE MINIMUM DESIGN LIMIT FOR THE SERVICE WATER SYSTEM. |
| CURRENTLY, LEVEL IS -6 FT 4 INCHES.  STEAM GENERATORS USING THE ATMOSPHERIC  |
| DUMPS ARE PROVIDING THE HEAT SINK FOR DECAY HEAT REMOVAL SINCE THE CONDENSER |
| IS NOT IN SERVICE.  ALL CONTROL RODS FULLY INSERTED FOLLOWING THE MANUAL     |
| TRIP.                                                                        |
|                                                                              |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.                         |
|                                                                              |
| *** UPDATE ON 1/21/00 @ 1339 BY KRAUSE TO GOULD ***                          |
|                                                                              |
| THE LICENSEE UPDATED THIS EVENT BY ALSO CLASSIFYING IT AS A RPS ACTUATION    |
| DUE  TO THE MANUAL REACTOR TRIP.                                             |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED.                                 |
|                                                                              |
| THE REG 3 RDO(HILLS) WAS NOTIFIED.                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36611       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  WA DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 01/21/2000|
|LICENSEE:  FEDERAL EXPRESS                      |NOTIFICATION TIME: 07:17[EST]|
|    CITY:  SEATTLE                  REGION:  4  |EVENT DATE:        01/14/2000|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  01/21/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LINDA SMITH          R4      |
|                                                |WAYNE HODGES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  TERRY FRAZEE (via e-mail)    |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| This is notification of an event in Washington state as investigated by the  |
| WA Department of Health, Division of Radiation Protection.                   |
|                                                                              |
| STATUS: new                                                                  |
|                                                                              |
| Reported By: Federal Express                                                 |
| City and state: Seattle, WA                                                  |
| License number: Not Applicable                                               |
| Type of license: General license for Commercial Carrier                      |
|                                                                              |
| Date of event: January 14, 2000                                              |
| Location of Event: Seattle-Tacoma International Airport                      |
|                                                                              |
| ABSTRACT: During off-loading a plane early in the morning of January 14,     |
| 2000, a two pound package containing 52 microcuries of I-125 labeled human   |
| insulin fell off the ramp loader and came to rest un-noticed under the       |
| extended ramp.  The ramp was lowered after the unloading of the plane,       |
| crushing the package.  The crushed package was discovered later that day and |
| Federal Express procedures were followed.  The package was noted to fall     |
| apart as it was lowered into the barrel overpack.  The state Division of     |
| Radiation Protection was notified promptly via 206-NUCLEAR (the state's      |
| radiation emergency line).  Staff from the Division responded and determined |
| that neither the individual who had overpacked the package nor the ramp      |
| loader were contaminated.  The barrel overpack was opened long enough to     |
| confirm the presence of removable contamination (approximately 2000 cpm per  |
| 100 sq. cm. using low energy gamma scintillation probe).  Direct survey      |
| reading inside of the barrel showed 30,000 to 50,000 cpm.  No contamination  |
| was found on the outside of the barrel or the barrel's storage location.     |
|                                                                              |
| The package was a Type A container labeled Yellow II with a transport index  |
| of 0.1 (UN2982, radioactive material, n.o.s.) shipped from Amersham          |
| Pharmacia Biotech to a Seattle research lab licensed by the state.           |
|                                                                              |
| What is the notification or reporting criteria involved?  Damaged package.   |
|                                                                              |
| Activity and isotope(s) involved:  52 microcuries of I-125.                  |
|                                                                              |
| Overexposures?  No individuals were exposed or contaminated as a result of   |
| this event.                                                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36612       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 01/21/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 11:17[EST]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        01/21/2000|
+------------------------------------------------+EVENT TIME:        10:48[EST]|
| NRC NOTIFIED BY:  GLENN HUTTON                 |LAST UPDATE DATE:  01/21/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |FELICIA HINSON       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     M/R        Y       65       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL REACTOR SCRAM PER PROCEDURE FOLLOWING TRIP OF ALL RECIRCULATION       |
| PUMPS                                                                        |
|                                                                              |
| During the performance of a surveillance, with a half scram signal inserted, |
| a spurious trip signal from the other system initiated a trip of all the     |
| reactor coolant system recirculation pumps.  The operators manually scrammed |
| the reactor per procedure, all rods fully inserted.  Heat removal is via the |
| main condenser with main feedwater feeding the reactor.  All systems         |
| functioned as designed and the plant is proceeding to cold shutdown.  A trip |
| review will be performed by the licensee.                                    |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36613       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 01/21/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 14:26[EST]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        01/21/2000|
+------------------------------------------------+EVENT TIME:        12:00[EST]|
| NRC NOTIFIED BY:  BROWNE                       |LAST UPDATE DATE:  01/21/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |FELICIA HINSON       R1      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Hot Shutdown     |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE LICENSEE NOTIFIED THE NEW JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION  |
| OF A FISH KILL.                                                              |
|                                                                              |
| THERE WAS A FISH KILL IN THE DISCHARGE CANAL OF MORE THAN 100 FISH (SEVERAL  |
| SPECIES) DUE TO COLD STRESS.  THIS OCCURRED FOLLOWING THE REACTOR SCRAM WHEN |
| COOLER WATER WAS DISCHARGED TO THE CANAL DECREASING ITS TEMPERATURE.         |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36614       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 01/21/2000|
|    UNIT:  [1] [2] []                STATE:  PA |NOTIFICATION TIME: 20:05[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        01/21/2000|
+------------------------------------------------+EVENT TIME:        19:45[EST]|
| NRC NOTIFIED BY:  THOMAS                       |LAST UPDATE DATE:  01/21/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHRIS CAHILL         R1      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(1)(ii)(A)  UNANALYZED COND OP     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INSUFFICIENT GUIDANCE FOR ENSURING THAT A SAFETY RELATED SYSTEM WAS          |
| OPERATING DURING A LOCA                                                      |
|                                                                              |
| During the evaluation of a separate Condition Report concerning a Technical  |
| Specification 3.0.3 entry involving the Beaver Valley Power Station (BVPS)   |
| Unit 1 Supplemental Leak Collection & Release System (SLCRS), it was         |
| discovered that the operators did not have sufficient guidance for ensuring  |
| that this safety related system was operating following an accident.         |
|                                                                              |
| BVPS Units 1 and 2 Technical Specifications 3/4.7.8 Bases states "System     |
| operation was assumed in that portion of the design basis accident LOCA      |
| analysis which addressed ESF leakage following the LOCA     Based on the     |
| results of the analyses, the SLCRS must be OPERABLE to ensure that ESF       |
| leakage following the postulated DBA LOCA   will not exceed 10CFR 100        |
| limits."  ESF leakage is a concern during a LOCA following a Safety          |
| Injection Transfer to Recirculation.                                         |
|                                                                              |
| The BVPS Unit 1 and 2 operators did not have sufficient guidance to ensure   |
| that a SLCRS fan is operating during a LOCA after Transfer to Recirculation  |
| occurs.  Thus, the SLCRS may not operate as assumed and credited in LOCA     |
| safety analyses.  SLCRS also provides cooling air flow to the emergency core |
| cooling pumps motors.  The need for SLCRS for maintaining the qualification  |
| of emergency core cooling pumps motors is proportional to the ambient        |
| outdoor air temperatures.  Current guidance does not ensure SLCRS would be   |
| available in all conditions where SLCRS flow is required to maintain the     |
| qualification of the emergency core cooling pump motors.                     |
|                                                                              |
| This condition is an unanalyzed condition and is reportable pursuant to      |
| 10CFR50.72(b)(1)(ii).                                                        |
|                                                                              |
| Verbal guidance has been provided to the BVPS Unit 1 and 2 operating crews   |
| to ensure a SLCRS fan is running in the event of a reactor trip or safety    |
| injection. This guidance is currently being formalized.                      |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36615       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 01/21/2000|
|    UNIT:  [] [] [3]                 STATE:  CT |NOTIFICATION TIME: 23:33[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        01/21/2000|
+------------------------------------------------+EVENT TIME:        23:13[EST]|
| NRC NOTIFIED BY:  JAMES V. GROGAN              |LAST UPDATE DATE:  01/21/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHRIS CAHILL         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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ULTIMATE HEAT SINK (UHS) BELOW MINIMUM DESIGN TEMPERATURE LIMIT OF 33        |
| DEGREES F (CONCERN IS SERVICE WATER TEMPERATURE).                            |
|                                                                              |
| Below is the Basis for Initial Reasonable Expectation of Continued           |
| Operability performed by Engineering:                                        |
|                                                                              |
| CCI is Closed Cooling for Safety Injection, CCE is Closed Cooling for        |
| Charging, SW is Service Water, and Hx is Heat Exchanger                      |
|                                                                              |
| "The concerns with low UHS temperature are pipe stress calculations and      |
| possible freezing of stagnant loops such as CCI and CCE.  Other portions of  |
| the SW system are not vulnerable to small changes in UHS temp due to         |
| constant flows and large heat sinks.  Additionally, the 33 degree F limit is |
| the design basis of the plant per the FSAR and therefore is reportable if    |
| exceeded.                                                                    |
|                                                                              |
| "CCL and CCE freezing:                                                       |
|                                                                              |
| "A review of the thermodynamic characteristics of the CCI and CCE heat       |
| exchangers, assuming UHS of 31 degrees F, shows that the temperature         |
| gradient of the process fluid, due to the high conductivity of the copper    |
| nickel pipe and room temperatures, results in CCI and CCE bulk fluid         |
| temperatures remaining above freezing for an extended period of time,        |
| although the bulk temperature of the shell side of the CCI heat exchangers   |
| is only  32.5 degrees F.  To assure operability of the SI pumps, the CCI     |
| system should be started at a SWP temperature of 33 degrees F decreasing to  |
| move the water through the system.  The historical UHS temperature dips      |
| below 33 degrees F have been for a short duration of hours followed by       |
| longer warming periods.  Design calculations show that CCI/SIH operate       |
| properly with the entire bulk temperature at 32 degrees F.  This is          |
| conservative as the majority of the CCI system will remain at ambient room   |
| temperature in the standby mode.  Once operating, there is additional heat   |
| input from the SIH pump.  Therefore, there is no limit to UHS temperature    |
| which would render CCI/SIH inoperable even over several hours.               |
|                                                                              |
| "A similar argument applies for the CCE/CHS system.  The temperature         |
| gradient and bulk temperature characteristics are identical.  Additionally,  |
| the CCE system utilizes a temperature control valve to maintain proper       |
| temperatures. The failed position of this valve (LOP) is to maximum flow     |
| through the SW Hx and has a position limiter designed for proper Charging    |
| lube oil temperature with a 33 degrees F UHS.  The supporting calculation    |
| demonstrates that a 41.9 degrees F CCE inlet temperature at the lube oil     |
| cooler results in a 55 degrees F lube oil temperature (minimum required      |
| temperature for charging pump operability).  If a service water temperature  |
| of 30 degrees F is used in the LMTD equation for the CCE HX, and the delta-T |
| on both the SW & CCE sides are assumed to remain unchanged, the calculated   |
| CCE inlet temperature at the lube oil cooler is 42.2 degrees F, which is >   |
| 41.9 degrees F needed for the 55 degrees F lube oil temperature.             |
|                                                                              |
| "To prevent potential freezing of the shell side fluid in the CCI heal       |
| exchangers and assure the Operability of the Safety Injection pumps, the CCL |
| pumps should be started at a SWP temperature of 33 degrees F decreasing.     |
|                                                                              |
| "Piping Stress:                                                              |
|                                                                              |
| "The Service Water System piping, supports and equipment have been analyzed  |
| to meet Code stress limits at a minimum temperature of 33 degrees F as       |
| described in OD MP3-213-96.  Lower temperatures will have no affect on the   |
| qualification status of the piping analysis since thermal expansion induced  |
| pipe stress is secondary, and is not evaluated under GL 91-18 Operability    |
| rules.                                                                       |
|                                                                              |
| "Increases in loads for pipe supports, equipment nozzles and equipment       |
| anchorage for temperatures below 33 degrees F are judged to be negligible    |
| and also have no affect on the operability of these components.  ERC         |
| MP3-DE-96-059 revision 1 transmitted Technical Report TR-89014-1, revision   |
| 2, which evaluated low temperature piping at Millstone Unit 3.  This report  |
| concludes that systems where the maximum operating temperature does not      |
| exceed 200 degrees F, and the temperature range does not exceed 200 degrees  |
| F, satisfy ASME Code requirements for thermal expansion loads. The Service   |
| Water maximum temperature range is well below 200 degrees F.                 |
|                                                                              |
| "Therefore, Service Water temperatures below 33 degrees F (to the freezing   |
| point of sea water 27.5 degrees F) will have no effect on the operability of |
| Service Water piping, supports, equipment nozzles, and equipment anchorage,  |
| from a stress standpoint.  No compensatory action are required.              |
|                                                                              |
| "An OD has been prepared to support continued operation of MP3 with a        |
| Service Water temperature of 31 degrees F.  This OD is stored on the MP3     |
| server at K:\DeptData\MacDeb\UHSOD.  Scoping calculations to support this OD |
| have been completed and reviewed. This OD must be reviewed and PORC approved |
| as required by the SM, if SWP temperatures lower than 33 degrees F are       |
| recorded."                                                                   |
|                                                                              |
| When the tide goes out the water temperature of the Ultimate Heat Sink       |
| temperature decreases and when the tide comes back in the temperature of the |
| Ultimate Heat Sink increases.  At the present time the tide is going out and |
| the water temperature is 32.7 degrees F.  In a couple of hours the tide will |
| start coming back in and the water temperature of the Ultimate Heat sink     |
| should increase to above 33 degrees F (37 to 38 degrees F).                  |
|                                                                              |
| The licensee notified State and Local Counties of this event.                |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36616       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 01/22/2000|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 05:55[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        01/22/2000|
+------------------------------------------------+EVENT TIME:        03:20[CST]|
| NRC NOTIFIED BY:  GEORGE D TURNER Jr.          |LAST UPDATE DATE:  01/22/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LINDA SMITH          R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       31       Power Operation  |31       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ESF ACTUATION OCCURRED  WHEN REACTOR CORE ISOLATION COOLING (RCIC) INBOARD   |
| STEAM SUPPLY VALVE CLOSED DURING TESTING.                                    |
|                                                                              |
| During the performance of routine surveillance testing of RCIC               |
| (STP-207-4538, "RCIC Isolation -RCIC Steam Supply Pressure Low Channel       |
| Functional Test"), an isolation of the inboard steam supply valve            |
| (E51-MOVF064) and the RCIC trip throttle valve (E51-C002) occurred.          |
|                                                                              |
| The Instrument and Controls Technician performing the test apparently        |
| misread step 7.1.3 and "N/A'd" the next step (7.1.4).  During the            |
| performance of subsequent steps, the isolation occurred because the          |
| isolation signal input from E31-N685A was not disabled.                      |
|                                                                              |
| The isolation signal was reset, RCIC was restored to standby in accordance   |
| with plant procedures.                                                       |
|                                                                              |
| All Emergency Core Cooling Systems remained operable during the time period  |
| RCIC was isolated.                                                           |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36617       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 01/22/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 16:58[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        01/22/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        13:00[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/22/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |DAVID HILLS          R3      |
|  DOCKET:  0707002                              |WAYNE HODGES         NMSS    |
+------------------------------------------------+JOSEPH GIITTER       IRO     |
| NRC NOTIFIED BY:  SPAETH                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FOUR HOUR 91-01 BULLETIN - NO NCS CONTROLS IN PLACE FOR A FISSILE MATERIAL   |
| OPERATION                                                                    |
|                                                                              |
| THE SHIFT SUPERINTENDENT'S OFFICE WAS NOTIFIED BY THE NUCLEAR CRITICALITY    |
| SAFETY STAFF THAT THEY HAD A FISSILE MATERIAL OPERATION FOR WHICH THERE WAS  |
| NO NUCLEAR CRITICALITY SAFETY APPROVAL IN PLACE.  THEY HAD A UF6 CYLINDER    |
| STORAGE AREA IN THE X-344A THAT HAD PREVIOUSLY BEEN  MARKED AS A DOE         |
| MATERIALS STORAGE AREA (DMSA).  IN REVIEW OF THE DMSA, THEY DISCOVERED THAT  |
| IT WAS NOT LISTED IN THE USEC/DOE LEASE AGREEMENT AS A DMSA.  SINCE NO DMSA  |
| WAS IDENTIFIED, USEC HAS THE RESPONSIBILITY FOR THE AREA INCLUDING           |
| RESPONSIBILITY FOR NUCLEAR CRITICALITY SAFETY COVERAGE.  THE AREA CONTAINED  |
| MULTIPLE SMALL UF6 CYLINDERS GROUPED TOGETHER WHICH CONTAINED GREATER THAN   |
| 15 GRAMS OF U-235 AT MORE THAN 1% ENRICHMENT.  THEREFORE, THE STORAGE AREA   |
| IS CONSIDERED TO BE A FISSILE MATERIAL OPERATION WITH NO NCSA IN PLACE TO    |
| ANALYZE THE CONDITIONS REQUIRED TO MAINTAIN NCS SAFETY.                      |
|                                                                              |
| THIS AREA WAS THOUGHT TO BE REGULATED BY DOE, BUT IT WAS LATER DETERMINED TO |
| BE USEC'S  RESPONSIBILITY AND USEC SHOULD HAVE HAD THE NCS INPLACE.          |
|                                                                              |
| THEY ARE NOT MOVING THE CYLINDERS, BUT THEY WILL BOUNDARY THE AREA OFF AND   |
| DEVELOP THEIR NCS CONTROLS.                                                  |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED AND THE DOE REPRESENTATIVE WILL BE   |
| NOTIFIED.                                                                    |
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