United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2000

Event Notification Report for December 21, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/20/2000 - 12/21/2000

                              ** EVENT NUMBERS **

37597  37621  37622  37623  37624  37625  37626  37627  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37597       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD                REGION:  3  |NOTIFICATION DATE: 12/14/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 18:33[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/14/2000|
+------------------------------------------------+EVENT TIME:        06:00[CST]|
| NRC NOTIFIED BY:  DAVID BRAGLIA                |LAST UPDATE DATE:  12/20/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OVERPOWER CONDITION DUE TO FEED TEMPERATURE CALCULATION ERROR                |
|                                                                              |
| "Braidwood Station Operating License condition 2.C.1 restricts licensed      |
| thermal power level to 3411 MW thermal. From December 13, 2000 at 0410 to    |
| December 14, 2000 at 0600, Braidwood Unit 2 was operated at a power level of |
| 100.55 percent in violation of this license condition.                       |
|                                                                              |
| "On December 14, 2000 at 0600 the station Thermal Performance Engineer       |
| discovered that Feedwater inlet temperature was not being calculated         |
| correctly by the plant process computer. Following a transfer of computer    |
| room ventilation trains on December 12, 2000 at 1800 feedwater calculated    |
| temperatures were 3F higher than actual feedwater temperatures. This        |
| resulted in the process computer calorimetric reading 0.6% low. Reactor      |
| power was adjusted using this incorrect calculation resulting in the         |
| overpower condition.                                                         |
|                                                                              |
| "Following identification of the error, Unit load was reduced to ensure that |
| reactor power was less than 100%. Nuclear instrumentation was verified to be |
| indicating less than 100%. No adjustment to the nuclear instrumentation was  |
| performed using the incorrect calculation.                                   |
|                                                                              |
| "This is being reported pursuant to License Condition 2.g, which requires    |
| notification within 24 hours of the violation of any condition in section    |
| 2.c of the Operating License."                                               |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| ***** UPDATE AT 1539 CST ON 12/20/00 FROM JIM ROYSTON TO LEIGH TROCINE       |
| *****                                                                        |
|                                                                              |
| The licensee is retracting this event notification.  The following text is a |
| portion of a facsimile received from the licensee:                           |
|                                                                              |
| "The initial report to the NRC (Event #37597) was based upon an observation  |
| of a 3F increase in the indicated Feedwater temperature (a primary input to |
| the Calorimetric calculation) following a Computer room temperature change   |
| initiated by a swap of the ventilation system.  An increase of 3F in        |
| Feedwater temperature results in a 0.55% reduction in Calorimetric power.  A |
| declining Calorimetric indication results in Operator action to increase and |
| maintain that indication at 100%.  Because of this, the initial indication   |
| was that the Unit was inadvertently increased to 100.55%."                   |
|                                                                              |
| "Upon execution of troubleshooting it was discovered that the temperature    |
| measurement problem was caused by miss-wired RTD temperature elements, which |
| are used to compensate thermocouples for their cold reference junction       |
| temperature.  From this data, a correction to the temperature measurements   |
| was performed such that the true Feedwater temperatures were determined      |
| during the event.  After applying this correction, it was determined that    |
| prior to the event the unit was operating at 99.488%.  Following the event,  |
| at the highest power level period, the unit was operating at 99.935%.  This  |
| data also confirms the conclusion that Unit 2 did not exceed 100% power.  As |
| an additional check, Calorimetric calculations were performed independently  |
| of those executed on the Plant Process Computer which indicate that no       |
| problems exist."                                                             |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R3DO (Kozak).                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37621       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 12/20/2000|
|    UNIT:  [] [2] []                 STATE:  WI |NOTIFICATION TIME: 06:31[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        12/20/2000|
+------------------------------------------------+EVENT TIME:        04:17[CST]|
| NRC NOTIFIED BY:  RANDY HASTINGS               |LAST UPDATE DATE:  12/20/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS KOZAK         R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     A/R        Y       63       Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP CAUSED BY TRANSFORMER GROUND      |
|                                                                              |
| The apparent cause of the reactor trip was a turbine trip caused by a ground |
| overcurrent relay actuation on the 2X01 transformer (main power out          |
| transformer).  Heat removal is via the steam dumps to the main condenser     |
| with main feedwater supplying the steam generators.  All systems operated as |
| required.  The licensee is investigating the cause of the ground             |
| indication.                                                                  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37622       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HADDAM NECK              REGION:  1  |NOTIFICATION DATE: 12/20/2000|
|    UNIT:  [1] [] []                 STATE:  CT |NOTIFICATION TIME: 11:37[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        12/20/2000|
+------------------------------------------------+EVENT TIME:        10:35[EST]|
| NRC NOTIFIED BY:  CHARLES REID                 |LAST UPDATE DATE:  12/20/2000|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANTHONY DIMITRIADIS  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        Decommissioned   |0        Decommissioned   |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO STATE DEP DUE TO OIL SPILL ON SITE                   |
|                                                                              |
| The licensee notified the Connecticut Department of Environmental Protection |
| (DEP) about an oil spill due to operator error.  The waste oil separator was |
| in operation filling a 55-gallon drum when the operator overflowed the drum. |
| The spill was contained on the concrete pad, there was no release offsite or |
| to the water.  Cleanup is now in progress.                                   |
|                                                                              |
| The licensee notified NRC Region 1 (John Wray).                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37623       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  SOUTHEAST MO STATE UNIVERSITY        |NOTIFICATION DATE: 12/20/2000|
|LICENSEE:  SOUTHEAST MO STATE UNIVERSITY        |NOTIFICATION TIME: 13:52[EST]|
|    CITY:  CAPE GIRARDEAU           REGION:  3  |EVENT DATE:        12/19/2000|
|  COUNTY:  CAPE GIRARDEAU            STATE:  MO |EVENT TIME:        13:30[CST]|
|LICENSE#:  24-09296-02           AGREEMENT:  N  |LAST UPDATE DATE:  12/20/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |THOMAS KOZAK         R3      |
|                                                |CHERYL TROTTIER      NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHRIS McGOWLAN               |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOST STRONTIUM-90 SOURCE                                                     |
|                                                                              |
| The school has lost a 20 mCi Sr-90 sealed source.  It is unknown how long it |
| has been missing.  A search of physical areas and records have been          |
| unsuccessful in locating the source.  As long as the source remains sealed   |
| it presents little of no threat to the public.                               |
|                                                                              |
| The source was used as part of an ionization cell for an ion capture         |
| detector.  The equipment was sold sometime back at auction.  The paperwork   |
| for the equipment does not indicate that the source was included in the      |
| sale.                                                                        |
|                                                                              |
| The school has been in contact with NRC Region 3 (Kevin Null).               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37624       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 12/20/2000|
|    UNIT:  [1] [2] []                STATE:  MI |NOTIFICATION TIME: 18:01[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/20/2000|
+------------------------------------------------+EVENT TIME:        08:55[EST]|
| NRC NOTIFIED BY:  DEAN BRUCK                   |LAST UPDATE DATE:  12/20/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS KOZAK         R3      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       0        Startup          |2        Startup          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FITNESS-FOR-DUTY REPORT REGARDING A NON-LICENSED SUPERVISOR'S RANDOM         |
| POSITIVE TEST FOR ALCOHOL                                                    |
|                                                                              |
| A non-licensed supervisor tested positive for alcohol during a random test.  |
| This was a first time positive test for this individual.  The individual was |
| removed from site, and the individual's badge was placed on administrative   |
| hold.                                                                        |
|                                                                              |
| The licensee made this 24-hour event notification in accordance with 10 CFR  |
| 26.73(a)(2)(iv).                                                             |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37625       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 12/20/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 19:04[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        12/20/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        13:05[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  12/20/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |THOMAS KOZAK         R3      |
|  DOCKET:  0707001                              |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC G. WALKER               |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 RESPONSE (24-HOUR REPORT) - LOSS OF ONE CONTROL IN THE    |
| DOUBLE CONTINGENCY                                                           |
|                                                                              |
| The following text is a portion of a facsimile received from the Paducah     |
| personnel:                                                                   |
|                                                                              |
| "The C-331 E and F surge drum room temperature was found to be at 103        |
| degrees F in violation of NCSA.CAS-005.  Requirement 3.2.6 of this NCSA      |
| states that when the surge drums contain UF6, they shall be operated at a    |
| minimum temperature of 105 degrees F.  This temperature requirement prevents |
| hydrogen fluoride (HF) from condensing at the maximum pressure rating of the |
| drums.  Should HF condense it could moderate any UF6 that might be           |
| present."                                                                    |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:"                                             |
|                                                                              |
| "HF cannot condense at 103 degrees F and 20 psia.  The drum pressures were   |
| all less than 1 psia; therefore, it was not possible to condense HF."        |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW           |
| CRITICALITY COULD OCCUR:"                                                    |
|                                                                              |
| "In order for a criticality to be possible, HF would have to condense.       |
| Therefore, the temperature of the drums would have to be less than 80        |
| degrees F, and the drum pressures would have to exceed 20 psia."             |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):"   |
|                                                                              |
| "[Since the double] contingency is based on two controls on moderation and   |
| [since] the temperature control was lost, double contingency was not         |
| maintained."                                                                 |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS    |
| LIMIT AND % WORST CASE CRITICAL MASS):"                                      |
|                                                                              |
| "The surge drums contain an estimated 1425 pounds of UF6 at less than 1      |
| weight % U235 assay."                                                        |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES:"                                            |
|                                                                              |
| "The first leg of double contingency is an administrative control, which     |
| limits the surge drum room temperature to a minimum of 105 degrees F.  The   |
| control was violated, and the first leg of double contingency was lost."     |
|                                                                              |
| "The second leg of double contingency is an administrative control to        |
| maintain the drum pressures below 20 psia, which is the maximum rated        |
| pressure for the drums.  This control was not violated, and this leg of      |
| double contingency was maintained."                                          |
|                                                                              |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS              |
| IMPLEMENTED:"                                                                |
|                                                                              |
| "Temperature loss was due to low outside ambient temperature.  Building      |
| temperature was raised and surge drum room temperature rose above minimum    |
| required temperature.  Additional heating for the area is being              |
| considered."                                                                 |
|                                                                              |
| Paducah personnel notified the NRC resident inspector.                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37626       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 12/20/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 22:25[EST]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        12/20/2000|
+------------------------------------------------+EVENT TIME:        20:14[EST]|
| NRC NOTIFIED BY:  ROBERT McCOY                 |LAST UPDATE DATE:  12/20/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANTHONY DIMITRIADIS  R1      |
|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       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC CONTROL ROOM VENTILATION SYSTEM SHIFT FROM NORMAL TO EMERGENCY     |
| RECIRCULATION MODE WHILE A PLANNED GAS DECAY TANK RELEASE WAS IN PROGRESS    |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 2014, with a gas decay tank release in progress (total activity 0.215    |
| Ci, (Kr-85 = 0.214 Ci, Xe-133 = 0.001 Ci)), control room ventilation gas     |
| monitor R-36 went into alarm causing ventilation to shift to mode F.  During |
| the [2-second] spike, R-36 counts went from 30 cpm to 856 cpm and back to 30 |
| cpm.  Local air samples taken by the RP Tech both in the control room and in |
| the area of the control room ventilation intake revealed no activity."       |
|                                                                              |
| The licensee stated that the gas decay tank release was planned and that the |
| counts going through the plant stack were considered normal.  (These counts  |
| peaked at 120 cpm.)  The licensee stated that the planned gas decay tank     |
| release was within both the expected and required release limits.  The wind  |
| was blowing in a favorable direction, and the stability class for            |
| meteorological conditions was stable.  Although counts have returned to      |
| normal, the licensee plans to leave control room ventilation in the          |
| emergency recirculation mode until tomorrow morning.                         |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37627       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 12/20/2000|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 22:58[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        12/20/2000|
+------------------------------------------------+EVENT TIME:        20:08[EST]|
| NRC NOTIFIED BY:  REINSBURROW                  |LAST UPDATE DATE:  12/20/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE ERNSTES         R2      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FAILURE OF A REACTOR CORE ISOLATION COOLING (RCIC) BYPASS TO CONDENSATE      |
| STORAGE TANK VALVE TO FULLY STROKE DURING STROKE TIME TESTING                |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "EVENT:  At 2008 on 12/20/00 during performance of OPT-10.1.8 (RCIC System   |
| Valve Operability Test), the 2-E51-F022 (RCIC bypass to condensate storage   |
| tank) failed to fully stroke during stroke timing of the valve.  A valve     |
| thermal overload annunciator was received.  This rendered the Brunswick Unit |
| 2 RCIC system inoperable.  RCIC was not in operation at the time of this     |
| failure."                                                                    |
|                                                                              |
| "INITIAL SAFETY SIGNIFICANCE EVALUATION:  Minimal safety significance.       |
| Remaining ECCS systems are operable."                                        |
|                                                                              |
| "CORRECTIVE ACTION(S):  Determine the cause of the 2-E51-F022 valve failure. |
| Return the Unit 2 RCIC system to operable following repair of 2-E51-F022."   |
|                                                                              |
| The licensee stated that this event did not result in any radiological       |
| release or reactor coolant leaks.  The licensee also stated that all systems |
| functioned as required and that there was nothing unusual or misunderstood.  |
| This event placed the unit in a 14-day technical specification limiting      |
| condition for operation.                                                     |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+