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Event Notification Report for March 30, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/29/2001 - 03/30/2001

                              ** EVENT NUMBERS **

37870  37871  37872  37873  37874  

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|Power Reactor                                    |Event Number:   37870       |
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| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 03/29/2001|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 07:55[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        03/29/2001|
+------------------------------------------------+EVENT TIME:        03:20[CST]|
| NRC NOTIFIED BY:  JOE LARUE                    |LAST UPDATE DATE:  03/29/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVE LOVELESS        R4      |
|10 CFR SECTION:                                 |                             |
|*COM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 6 EMERGENCY PLAN SIRENS                                              |
|                                                                              |
| The licensee had a problem with the 69 kV power grid in southern Coffey      |
| County, which in turn caused the loss of 6 emergency plan sirens at 0220 CST |
| on 3/29/01.  At 0320 CST, the criteria for making a 10 CFR 50.72 report on a |
| major loss of emergency communications was met.  At 0432 CST the sirens were |
| restored to normal operation.                                                |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
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|Power Reactor                                    |Event Number:   37871       |
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| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 03/29/2001|
|    UNIT:  [] [2] []                 STATE:  CT |NOTIFICATION TIME: 13:43[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        01/31/2001|
+------------------------------------------------+EVENT TIME:        15:59[EST]|
| NRC NOTIFIED BY:  HUFF                         |LAST UPDATE DATE:  03/29/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHELE EVANS        R1      |
|10 CFR SECTION:                                 |ED GOODWIN           EO      |
|*INV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| INVALID ACTUATION OF THE "A" EMERGENCY DIESEL GENERATOR                      |
|                                                                              |
| On January 31, 2001 at 1559 while performing an air roll of the "A"          |
| Emergency Diesel Generator (EDG) as part of the restoration of the EDG to an |
| operable status, the EDG started.  This occurred because the fuel racks were |
| not properly tripped as required by the operating procedure.  The operator   |
| had attempted to trip the fuel racks, but did not hit the trip button with   |
| sufficient force to trip the racks.  As a result the EDG started and came up |
| to speed, but the EDG did not progress through the loading sequence since    |
| there was no loss of power.  Control Room personnel were immediately         |
| notified and the EDG was properly shutdown by initiating an emergency trip   |
| from the Control Room.                                                       |
|                                                                              |
| The actuation of the EDG occurred due to human error and procedural          |
| inadequacy and was not due to actual plant conditions.  Therefore, the       |
| actuation was not a valid actuation. The "A" EDG had been declared           |
| inoperable under Technical Specification 3.8.1.1.b to perform a six hour     |
| loaded run.  10CFR50.73(a)(2)(iv) excludes reporting an invalid actuation if |
| the equipment is properly taken out of service.  However, the EDG was "not   |
| properly taken out of service" at the time as described in NUREG-1022 to     |
| qualify for the exclusion to reporting the invalid actuation.   Although the |
| EDG had been declared inoperable, it was still "available".  If an           |
| Engineered Safeguards Actuation System (ESAS) signal had occurred, the EDG   |
| would have been available to perform its function.  In order to qualify for  |
| the exclusion from reporting this invalid actuation, the undervoltage start  |
| capability from ESAS would have to have been defeated, the flow of fuel to   |
| the EDG stopped, or other appropriate action taken.  Therefore, this event   |
| is reportable as a 60-day ENS phone call.                                    |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
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+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   37872       |
+------------------------------------------------------------------------------+
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 03/29/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 14:22[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/29/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        10:45[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/29/2001|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |BRUCE BURGESS        R3      |
|  DOCKET:  0707002                              |FRITZ STURZ          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  SPAETH                       |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| HIGH LEVEL CONDENSATE PROBES ACTIVATED ON AUTOCLAVE #4                       |
|                                                                              |
| At 1045 hours on 03/29/01, both the "A" and "B" High Level Condensate probes |
| activated on Autoclave #4 in the X-344 UF6 Sampling Facility causing a High  |
| Condensate Alarm.  The activation of either of these probes will cause the   |
| autoclave steam supply valves ( "Q" components) to actuate (close).  The     |
| steam supply valves closed, as designed, autoclave #4 was in TSR Mode II     |
| (HEATING) at the time of the alarm activation. Operations personnel          |
| immediately responded to the alarm in accordance with the approved Alarm     |
| Response Procedures.  The alarm reset when operations personnel drained      |
| excess condensate from autoclave drain line, and then acknowledged the alarm |
| at the local autoclave control panel.  All autoclave (and cylinder)          |
| operating parameters were determined to be within normal ranges.  Autoclave  |
| #4 was placed in TSR mode VII (Shutdown) by operations personnel and         |
| declared inoperable by the Plant Shift Superintendent.  Based on the         |
| actuation of both High Level Condensate probes, this event is being reported |
| as a valid safety system actuation, a 24 hour NRC  event.  An Engineering    |
| Evaluation has been requested to investigate the circumstances surrounding   |
| this safety actuation.                                                       |
|                                                                              |
| The DOE Representative will be informed.  Reg 3 (Monty Phillips) was         |
| notified.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37873       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 03/29/2001|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 14:42[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        03/29/2001|
+------------------------------------------------+EVENT TIME:        11:00[EST]|
| NRC NOTIFIED BY:  RABENOLD                     |LAST UPDATE DATE:  03/29/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|*DEG 50.72(b)(3)(ii)(A)  DEGRAD COND DURING OP  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       84       Power Operation  |84       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SECONDARY CONTAINMENT BYPASS LEAKAGE FAILED TO MEET ACCEPTANCE CRITERIA      |
|                                                                              |
| During the reportability review of Condition Report 01-1582 it was           |
| identified that a degraded condition had existed that is required to be      |
| reported per 10 CFR 50.72 (b)(3)(ii).  It was confirmed that Secondary       |
| Containment Bypass leakage did not meet the acceptance criteria of less than |
| or equal to 0.0504 La for Type B and C LLRTs. Specifically the minimum       |
| pathway leakage limit is 4340 sccm, however, the as found value was 20,653   |
| sccm (adjusted for instrument accuracy). The dominant leakage (18,110 sccm)  |
| was from the High Pressure Core Spray Valve 1 E22-F0012, packing.  The       |
| penetration for this system credits the 1 E22-F0012 (located outside         |
| Containment) as the inboard barrier and the closed system as the outboard    |
| barrier, therefore, packing leakage in this case results in minimum pathway  |
| leakage. The plant was in Refuel Outage 8 when the leakage was identified.   |
| The valve has since been repacked and the current leakage is within limits.  |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37874       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  FRAMATOME ANP RICHLAND INC           |NOTIFICATION DATE: 03/29/2001|
|LICENSEE:  FRAMATOME ANP RICHLAND INC           |NOTIFICATION TIME: 17:58[EST]|
|    CITY:  RICHLAND                 REGION:  4  |EVENT DATE:        03/29/2001|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PST]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  03/29/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |DAVE LOVELESS        R4      |
|                                                |BRUCE BURGESS        R3      |
+------------------------------------------------+MICHELE EVANS        R1      |
| NRC NOTIFIED BY:  MALLAY                       |VERN HODGE           NRR     |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PART 21 -  AN INCORRECT COMPUTER CODE WAS SUPPLIED BY FRAMATOME TO FOUR      |
| LICENSEES                                                                    |
| FOR CALCULATION OF THE MINIMUM CRITICAL POWER RATIO (MCPR)                   |
|                                                                              |
| In the performance of the analysis used to establish the MCPR operating      |
| limits, the use of an inappropriate reference temperature resulted in an     |
| overprediction of the thermal conductivity of the fuel. This overprediction  |
| produced MCPR operating limits that were lower than they should have been.   |
| Therefore, the MCPR limits must be raised by up to 0.01 or 0.02, depending   |
| on the affected power plants.                                                |
|                                                                              |
| The MCPR must be raised by up to 0.01 from the limits previously provided    |
| for Dresden Units 2 and 3, and for Quad Cities Units 1 and 2. The MCPR       |
| limits for LaSalle Units 1 and 2 must be revised by up to 0.01 for power     |
| levels of 60 percent and above and by up to 002 below 60 percent.            |
| Calculations for Susquehanna Units 1 and 2 were affected but the MCPR limits |
| were unchanged. Continued compliance with the over-pressurization criteria   |
| specified by the ASME code has been demonstrated.                            |
|                                                                              |
| All units, including Susquehanna, have been notified. Compensatory measures  |
| have been provided to the affected plants until confirmatory analyses have   |
| been completed. The appropriate reference temperature has been installed in  |
| the computer code used for the MCPR analysis.                                |
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