Event Notification Report for December 26, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/22/2000 - 12/26/2000

                              ** EVENT NUMBERS **

37630  37631  37632  

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|Power Reactor                                    |Event Number:   37630       |
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| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 12/22/2000|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 11:29[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        12/22/2000|
+------------------------------------------------+EVENT TIME:        09:45[CST]|
| NRC NOTIFIED BY:  RICK HUBBARD                 |LAST UPDATE DATE:  12/22/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BILL JONES           R4      |
|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          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| LOSS OF POWER TO THE TECHNICAL SUPPORT CENTER (TSC)                          |
|                                                                              |
| Breaker 13-40 tripped with the ground flag dropped.  This breaker supplies   |
| primary power to the TSC.  There is a backup diesel generator available to   |
| supply power to the TSC but will not be energized until it is determined     |
| that there is no ground at the TSC.  Once the TSC D/G is energized the       |
| facility will once again be available.                                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * Update at 1150 on 12/22/00 by Hubbard received by Weaver * * *         |
|                                                                              |
| The diesel generator is now supplying the TSC with electrical power (as of   |
| 1041 CST).  Investigation continues into why breaker 13-40 tripped.          |
|                                                                              |
| Notified the R4DO(Jones).                                                    |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37631       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 12/22/2000|
|    UNIT:  [] [2] []                 STATE:  AL |NOTIFICATION TIME: 16:54[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        12/22/2000|
+------------------------------------------------+EVENT TIME:        12:25[CST]|
| NRC NOTIFIED BY:  NACOSTE                      |LAST UPDATE DATE:  12/23/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE ERNSTES         R2      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD  |                             |
|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                                   
+------------------------------------------------------------------------------+
| PLANT ENTERED 14 DAY LCO DUE TO HIGH PRESSURE COOLANT INJECTION BEING        |
| INOPERABLE                                                                   |
|                                                                              |
| HPCI was declared inoperable after failing testing.  During the performance  |
| of 2-SI-3.5.1.7 HPCI MAIN AND BOOSTER PUMP SET DEVELOPED HEAD AND FLOW RATE  |
| TEST AT RATED REACTOR PRESSURE, the HPCI system could not be verified to be  |
| vented.                                                                      |
|                                                                              |
| The probable reason for not being able to make this verification is due to a |
| faulty flow gauge in the HPCI piping system.                                 |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
|                                                                              |
| * * * RETRACTED AT 0240 EST 0N 12/23/00 BY MICKEY HUNTER TO FANGIE JONES * * |
| *                                                                            |
|                                                                              |
| "The 4 hour report made in accordance with 10CFR50.72.b.2.iii at 1630 on     |
| 12/22/2000 is being retracted for the following reasons:  During the         |
| performance of 2-SR-3.5.1.7 HPCI MAIN AND BOOSTER PUMP SET DEVELOPED HEAD    |
| AND FLOW RATE TEST AT RATED REACTOR PRESSURE, there were indications of flow |
| through the vent line during initial Surveillance testing however; the test  |
| methodology used in the Surveillance could not verify that flow. We revised  |
| the Surveillance methodology to prescribe an alternate process of            |
| determining flow. The Surveillance test was reperformed satisfactorily and   |
| verified indications of flow that was observed in the previous performance   |
| of the Surveillance test. Thus this proved operability of HPCI during        |
| previous performance of Surveillance test."                                  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The R2DO (Mike Ernstses)  |
| was notified.                                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37632       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 12/23/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 15:02[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        12/23/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        06:15[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  12/23/2000|
|    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:  BEASLEY                      |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| FACILITY HAS PROBLEMS WITH FREEZING STANDPIPES THAT SUPPLY WATER TO THEIR    |
| HIGH PRESSURE FIRE WATER SYSTEMS.                                            |
|                                                                              |
| During a discussion between the Paducah and Portsmouth Plant Shift           |
| Superintendents (PSS), the Portsmouth PSS stated that their facility was     |
| having a problem with the standpipes freezing that supply water to their     |
| High Pressure Fire Water (HPFW) systems.  Following this discussion, the     |
| Paducah PSS instructed all building managers containing HPFW systems to      |
| check the temperatures of the standpipes.  Following this temperature        |
| survey, two systems in the C-337 building were discovered to have abnormally |
| low temperatures.  In order to verify operability, Fire Services personnel   |
| performed flow tests on these two systems.  During this testing, it was      |
| discovered that the standpipe for HPFW system D-2 was frozen, and the system |
| could not perform its specified safety function.  The High Pressure Fire     |
| Water System is required to be operable according to TSR 2.4.4.5. HPFW       |
| system D-2 was declared inoperable at 0615 on 12-23-00, and a fire patrol    |
| was initiated as required by the TSR.  During follow up investigation, it    |
| was discovered that six of the eight exhaust fans and a section of           |
| recirculating louvers that supply heat to this area were not functioning.    |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector has been notified of this event.                  |
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