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Event Notification Report for August 10, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           08/09/2001 - 08/10/2001

                              ** EVENT NUMBERS **

38173  38186  38193  38194  38195  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   38173       |
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| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 07/25/2001|
|    UNIT:  [1] [2] []                STATE:  TX |NOTIFICATION TIME: 19:02[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        07/25/2001|
+------------------------------------------------+EVENT TIME:        10:11[CDT]|
| NRC NOTIFIED BY:  WAYNE HARRISON               |LAST UPDATE DATE:  08/09/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GARY SANBORN         R4      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| POTENTIAL TO DRAIN AFW STORAGE TANK DURING PLANT FLOODING SCENARIO           |
|                                                                              |
| "STPNOC Engineering identified a condition outside the station's design      |
| basis that has been determined to be reportable under 10CFR50.73(a)(2)(ii)   |
| as an unanalyzed condition that significantly degraded plant safety.         |
| Notification is required by 10CFR50.72(b)(3)(ii)(B).                         |
|                                                                              |
| "During review of design calculations, a new internal flooding condition was |
| identified that could have resulted in depletion of the AFW Storage Tank to  |
| the point where the plant would not be able to transition from AFW to RHR as |
| designed. Each of STP's four trains of AFW is enclosed in its own            |
| water-tight compartment directly beneath its associated MFW line RCB         |
| penetration. Operator response to a main feedline break includes isolation   |
| of the faulted steam generator, including AFW. If the MFW break is           |
| postulated to occur in the MFW penetration area above AFW, the AFW cubicle   |
| beneath the break will flood. In the case of the D train steam-driven AFW,   |
| the water level will submerge the turbine-driven AFW pump, its trip/throttle |
| valve and AFW isolation valves in about 6 to 30 minutes, depending on break  |
| size. As a consequence of the accident, the submerged motor-operated valves  |
| are assumed to fail as-is, supplying steam to the turbine-driven pump and    |
| allowing AFW flow. In addition, the analysis assumes the single failure of   |
| one unsubmerged steam supply isolation valve. The steam-driven pump will     |
| continue to function while submerged and continue to take suction from the   |
| AFWST and expel it out the break. Unless the pump is secured, its continued  |
| operation could accelerate the depletion of the AFWST to the point that the  |
| plant would not be able to transition from AFW to RHR as designed. This      |
| condition affects only the D train steam-driven AFW. Trains A, B, and C are  |
| motor driven and can be readily secured at their power source if necessary.  |
|                                                                              |
| "Compensatory action is being taken to implement a temporary modification to |
| allow operator action to isolate the AFW supply to the steam-driven AFW pump |
| at the AFWST."                                                               |
|                                                                              |
| The NRC resident inspector has been informed of this condition by the        |
| licensee.                                                                    |
|                                                                              |
| ***** RETRACTION FROM WAYNE HARRISON TO L. TROCINE RECEIVED AT 1507 EDT ON   |
| 08/09/01 *****                                                               |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[...]  This notification is RETRACTED.  The break described above is in a   |
| break exclusion zone and is the non-mechanistic break required by the        |
| Standard Review Plan to be postulated for the purpose of defining the        |
| environmental conditions for qualification of equipment.  Consideration of a |
| single failure with this non-mechanistic break is not required.              |
| Consequently, the unsubmerged steam supply valve may be assumed to function  |
| to isolate steam to the turbine-driven AFW pump and there is not a condition |
| that significantly degrades plant safety."                                   |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  The NRC operations |
| officer notified the R4DO (Charles Marschall).                               |
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|Power Reactor                                    |Event Number:   38186       |
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| FACILITY: DIABLO CANYON            REGION:  4  |NOTIFICATION DATE: 08/04/2001|
|    UNIT:  [1] [2] []                STATE:  CA |NOTIFICATION TIME: 19:55[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        08/04/2001|
+------------------------------------------------+EVENT TIME:        15:22[PDT]|
| NRC NOTIFIED BY:  DAVID BAHNER                 |LAST UPDATE DATE:  08/09/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CHUCK CAIN           R4      |
|10 CFR SECTION:                                 |HERB BERKOW          NRR     |
|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| AUTOMATIC START OF BOTH UNITS DIESEL GENERATORS DUE TO A LOSS OF START-UP    |
| POWER                                                                        |
|                                                                              |
| "Electrical fault caused loss of Start-up Power to both units.  This caused  |
| all six [6] diesel generators on both units to automatically start."         |
|                                                                              |
| Circuit breaker CB212 which supplies 230KV start-up power to both units      |
| opened due to an unidentified electrical fault.  Initial indication was a    |
| loss of power to outbuildings onsite followed about twenty-two (22) minutes  |
| later with a loss of power to the Start-up transformers.  Investigation      |
| found the grounding fuses on the Unit 1 side open.  Should a unit trip occur |
| while in this condition, RCS cooldown by natural circulation would be        |
| required.                                                                    |
|                                                                              |
| Both units are in Tech Spec LCO 3.8.1 Condition 'A' which requires           |
| restoration of start-up power within 72-hours or unit shutdown; mode 3 (hot  |
| standby) in the following 6-hours followed by mode 5 (cold shutdown)         |
| 36-hours later.  The licensee is performing a maintenance and engineering    |
| evaluation to determine if start-up can be restored by closing a cross-tie   |
| breaker from Unit 2.                                                         |
|                                                                              |
| None of the diesel generators loaded and all have been secured and returned  |
| to standby.                                                                  |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
|                                                                              |
| ***** UPDATE FROM JEFF KNISLEY TO LEIGH TROCINE RECEIVED AT 1759 EDT ON      |
| 08/09/01 *****                                                               |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[...]  FOLLOW-UP INFORMATION"                                               |
|                                                                              |
| "The event, as described in the original event notification number 38186,    |
| caused all six diesel generators on both units to automatically start.  The  |
| diesel generators started, as designed, upon receiving an anticipatory       |
| signal due to the loss of Start-Up Power; and the diesel generators did not  |
| load, as designed, because vital and non vital power was still available     |
| from the Auxiliary Transformers, back-fed from the generator output of each  |
| unit."                                                                       |
|                                                                              |
| "As stated in the original event notification, the grounding fuses for the   |
| Unit 1 Start-Up Transformer were found open.  The immediate cause of the     |
| event was a fault in the 12kV Fuse Cabinet for the Unit 1 Start-Up           |
| Transformer ground resistor.  The ground resistor was observed to be         |
| radiating heat just prior to the event witnessed by the damage to the Fuse   |
| Cabinet.  The cause of this failure is being investigated within the         |
| corrective action program."                                                  |
|                                                                              |
| "As stated in the original event notification, there was a loss of power to  |
| outbuildings onsite.  The 12kV underground distribution breaker tripped [on  |
| 08/04/01 at] 1500 PDT, causing the loss of non-essential site loads; such as |
| the Administration, Training and Maintenance Buildings, and support          |
| facilities -supporting power production including water treatment for        |
| Condensate make-up, back-up Service Air Compressors, and Radwaste Laundry    |
| Building."                                                                   |
|                                                                              |
| "Start-Up power to Unit 2 was restored [on 08/05/01 at] 0513 PDT.  After     |
| assuring there was no damage to the Unit 1 Start-Up Bus, power was restored  |
| to the Unit 1 Start-Up Bus [on 08/06/01 at] 1122 PDT, via a cross-tie        |
| breaker from the Unit 2 Start-Up Transformer.  The 12kV underground loop was |
| reenergized [on 08/07/01], thus restoring power to the non-essential site    |
| loads.  Repair of the Fuse Cabinet is in progress."                          |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R4DO (Charles Marschall).                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38193       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ARKANSAS DEPARTMENT OF HEALTH        |NOTIFICATION DATE: 08/09/2001|
|LICENSEE:  GREEN BAY PACKAGING                  |NOTIFICATION TIME: 14:22[EDT]|
|    CITY:  MORRILTON                REGION:  4  |EVENT DATE:        08/07/2001|
|  COUNTY:                            STATE:  AR |EVENT TIME:             [CDT]|
|LICENSE#:  ARK197BP01-98         AGREEMENT:  Y  |LAST UPDATE DATE:  08/09/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHARLES MARSCHALL    R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JARED THOMPSON (fax)         |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT REGARDING A DAMAGED NDC GAUGE CONTAINING              |
| AMERICIUM-241 AT                                                             |
| GREEN BAY PACKAGING IN MORRILTON, ARKANSAS                                   |
|                                                                              |
| The following text is a portion of a facsimile received from the Arkansas    |
| Department of Health:                                                        |
|                                                                              |
| "The Department received notified on August 8, 2001, that a gauge containing |
| radioactive material was damaged during maintenance operations at Green Bay  |
| Packaging in Morrilton, Arkansas.  The gauge is licensed under Arkansas      |
| Radioactive Material License Number ARK-197-BP-01-98."                       |
|                                                                              |
| "The incident occurred on August 7, 2001, when the gauge became caught in    |
| the conveyor wire and was pulled away from the mounting bracket, falling and |
| striking a roller.  The impact tore the shutter from the gauge.  The gauge   |
| was retrieved without exposure to personnel.  Temporary shielding was added  |
| to the gauge, and the gauge was placed in storage by the Radiation Safety    |
| Officer."                                                                    |
|                                                                              |
| "It was determined that the source was intact, and a leak test was           |
| performed.  The gauge is to be returned to the manufacturer."                |
|                                                                              |
| "The gauge is [an] NDC Model Number 104F, Serial Number 12605, containing    |
| 0.93 gBq (21 mCi) of Americium-241."                                         |
|                                                                              |
| "The Department is conducting an investigation of the incident."             |
|                                                                              |
| (Call the NRC operations officer for contact information.)                   |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38194       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 08/09/2001|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 18:18[EDT]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        08/09/2001|
+------------------------------------------------+EVENT TIME:        16:01[EDT]|
| NRC NOTIFIED BY:  ERIC DeMONCH                 |LAST UPDATE DATE:  08/09/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DANIEL HOLODY        R1      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |93       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING APPROVAL TO EXCEED THE NORMAL OPERATING       |
| DISCHARGE TEMPERATURE PERMIT LIMIT DUE TO THE EMERGENCY NEED FOR POWER AND   |
| CONDITIONS ON THE GRID                                                       |
|                                                                              |
| At approximately 1500, the licensee began to reduce reactor power from 100%  |
| because main condenser discharge temperature began to approach the discharge |
| permit temperature limit of 106F.  At 1601, the system dispatcher notified  |
| the licensee of an emergency need for power and informed the licensee that   |
| the criteria to exceed the discharge permit temperature limit was            |
| authorized.  In this condition, a discharge temperature of 110F is allowed. |
| As a result, the licensee ceased the power reduction with the unit at        |
| approximately 98% reactor power and returned reactor power to 100%.          |
|                                                                              |
| The emergency need for power was cancelled at 1612.  As a result, the        |
| licensee commenced another power reduction in order to reduce the main       |
| condenser discharge temperature and comply with the 106F discharge permit   |
| limit.                                                                       |
|                                                                              |
| The highest main condenser discharge temperature attained was 106.36F.      |
| Reactor power is currently stable at 93%.                                    |
|                                                                              |
| The licensee notified the New Jersey Department of Environmental Protection  |
| and plans to notify the NRC resident inspector.                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38195       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES                REGION:  3  |NOTIFICATION DATE: 08/09/2001|
|    UNIT:  [1] [] []                 STATE:  MI |NOTIFICATION TIME: 21:37[EDT]|
|   RXTYPE: [1] CE                               |EVENT DATE:        08/09/2001|
+------------------------------------------------+EVENT TIME:        20:00[EDT]|
| NRC NOTIFIED BY:  MARK HOLBEIN                 |LAST UPDATE DATE:  08/09/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANNE MARIE STONE     R3      |
|10 CFR SECTION:                                 |                             |
|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY THAT SUPPORTS MAY NOT BE CAPABLE OF PROPERLY RESTRAINING THE       |
| MISSILE SHIELD DURING A DESIGN BASIS SEISMIC EVENT                           |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Evaluation of the Missile Shield, over the Reactor Vessel Head, has         |
| revealed that the supports for the Missile Shield may not be capable of      |
| properly restraining the Missile [Shield] in the horizontal direction during |
| a Design Basis Seismic Event.  Consequently the Missile Shield is considered |
| inoperable pending further evaluation.  This is being reported as an         |
| unanalyzed condition that could significantly degrade Plant safety."         |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+