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Event Notification Report for June 14, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/13/2001 - 06/14/2001

                              ** EVENT NUMBERS **

37933  38066  38067  38068  38069  38070  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37933       |
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| FACILITY: KEWAUNEE                 REGION:  3  |NOTIFICATION DATE: 04/19/2001|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 17:24[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        04/19/2001|
+------------------------------------------------+EVENT TIME:        14:40[CDT]|
| NRC NOTIFIED BY:  BRADLY MCMAHON               |LAST UPDATE DATE:  06/13/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |RONALD GARDNER       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          Y       96       Power Operation  |96       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| DEGRADED APPENDIX "R" FIRE BARRIER                                           |
|                                                                              |
| While conducting a walk down inspection of 10CFR50 Appendix R Barriers, two  |
| degraded gypsum walls were identified. The two walls are intended to serve   |
| as three hour rated Appendix R barriers.  The inspection of the walls        |
| revealed that a segment of the walls approximately 6 feet by 6 inches was    |
| not constructed as required.  The two walls provide separation of safe       |
| shutdown equipment in the event of an Appendix R design basis fire.  The     |
| walls separate the charging pumps, a dedicated shutdown system component,    |
| from the safety injection pumps which are alternate shutdown system          |
| equipment.                                                                   |
|                                                                              |
| Although the walls are not constructed as designed, they appear to be        |
| completed to about 75% of design and are judged capable of providing some    |
| protection.  Nevertheless, the walls are declared inoperable and             |
| compensatory actions according to the Kewaunee Fire Plan have been           |
| initiated.  The walls are declared inoperable due to not having any          |
| documented analysis to support the design basis rating.                      |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE AT 1517 ON 6/13/01 BY HARRINGTON RECEIVED BY WEAVER * * *       |
|                                                                              |
| The licensee has retracted this event based upon further review.  On 4/19/01 |
| Kewaunee Nuclear Power Plant (KNPP) reported to NRC via the Event            |
| Notification System (ENS) an unanalyzed condition related to two Appendix R  |
| fire barriers. The report was made based on a cursory visual inspection of   |
| two barriers that appeared to be missing a portion of a layer of gypsum      |
| board.  Based on what appeared to be less than the three required layers of  |
| gypsum board, a conservative assumption was made that the barriers did not   |
| meet design requirements.  Since the ENS report was filed, the barriers were |
| partially disassembled to gather data for-performing a fire hazards analysis |
| of the apparently degraded barriers in accordance with Generic Letter 86-10. |
| Disassembling the barriers revealed that what appeared to be a partially     |
| missing layer was in fact an additional partial layer of gypsum board.       |
|                                                                              |
| Based on the additional data gathered from disassembling the barriers, the   |
| barriers met design requirements for a three hour rated Appendix R fire      |
| barrier.  Therefore, the barriers were not degraded and an unanalyzed        |
| condition never existed. Consequently, the reporting criteria for an         |
| unanalyzed condition was not exceeded and is the basis for retracting the    |
| ENS report notification made on 4/19/01.                                     |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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|Other Nuclear Material                           |Event Number:   38066       |
+------------------------------------------------------------------------------+
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| REP ORG:  MT DEPARTMENT OF TRANSPORTATION      |NOTIFICATION DATE: 06/13/2001|
|LICENSEE:  MT DEPARTMENT OF TRANSPORTATION      |NOTIFICATION TIME: 10:02[EDT]|
|    CITY:  GREAT FALLS              REGION:  4  |EVENT DATE:        06/12/2001|
|  COUNTY:                            STATE:  MT |EVENT TIME:        08:15[MDT]|
|LICENSE#:  25-11498-01           AGREEMENT:  N  |LAST UPDATE DATE:  06/13/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN PELLET          R4      |
|                                                |FRED BROWN           NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  REX HOY                      |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DAMAGED MOISTURE/DENSITY GAUGE                                               |
|                                                                              |
| A Troxler Model 3440 moisture/density gauge (s/n 25332), containing one 8    |
| mCi Cs-137 and one 40 mCi Am-241/Be sources,  was slightly damaged when it   |
| was struck by a roller. The area surrounding the gauge was immediately roped |
| off until the gauge could be surveyed.  The licensee stated that the sources |
| were retracted at the time of the event and results of surveys and wipe      |
| tests were negative.  The damage appears to be limited to a slight denting   |
| of the plastic cover.  The licensee has visually inspected the sources but   |
| did not observe any damage.                                                  |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38067       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 06/13/2001|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 10:57[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        05/12/2001|
+------------------------------------------------+EVENT TIME:        16:53[EDT]|
| NRC NOTIFIED BY:  ERIC OLSON                   |LAST UPDATE DATE:  06/13/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANIELLO DELLA GRECA  R1      |
|10 CFR SECTION:                                 |                             |
|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 60 DAY OPTIONAL REPORT IN ACCORDANCE WITH 10 CFR 50.73(a)(1)                 |
|                                                                              |
| "During performance of a loss of offsite power test with a LOCA, an          |
| automatic start of the A and B emergency diesel generators, the A and B core |
| spray systems, and the A, B, C and D low pressure coolant injection pumps    |
| occurred.  All actuations were complete and functioned as designed.  The     |
| start was inadvertent and occurred when a 125 VDC knife blade was closed.    |
| The switch was installed as part of the procedure and was wired incorrectly  |
| such that when it was closed it caused an inadvertent LOCA signal to the     |
| affected systems."                                                           |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38068       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 06/13/2001|
|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 11:21[EDT]|
|   RXTYPE: [2] GE-4                             |EVENT DATE:        06/13/2001|
+------------------------------------------------+EVENT TIME:        05:30[EDT]|
| NRC NOTIFIED BY:  HARRY B. GILES               |LAST UPDATE DATE:  06/13/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |ANNE BOLAND          R2      |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |JOHN HICKEY          NMSS    |
|                                                |JOHN TAPPERT         NRR     |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| TRANSPORTATION REPORT INVOLVING RAD WASTE SHIPMENT FROM FERMI TO BARNWELL,   |
| SOUTH CAROLINA                                                               |
|                                                                              |
| "Event notification resulting from an offsite notification of a              |
| transportation accident involving a radioactive waste shipment from Fermi 2  |
| to Barnwell, South Carolina. NRC reportable under 10CFR50.72(b)(2)(xi) any   |
| event or situation for which notification to other government agencies has   |
| been made.                                                                   |
|                                                                              |
| "At approximately 0530 hours on 06-13-2001, a Hittman Transport vehicle      |
| transporting Class 'A' radioactive waste material [proper shipping name:     |
| Radioactive Material, Low Specific Activity, n.o.s. 7, UN2912, Fissile       |
| Excepted, Compacted Dry Active Waste] from Enrico Fermi 2 facility to        |
| Barnwell, SC was involved in a vehicle accident west of Columbia, South      |
| Carolina.                                                                    |
|                                                                              |
| "Hittman Transport notified the South Carolina Department of Health and      |
| Environmental Control at approximately 0805 hours on 06-13-2001 concerning   |
| the transportation accident. Hittman Transport also notified Fermi 2 at      |
| approximately 0810 hours on 06-13-2001 of the vehicle accident.              |
|                                                                              |
| "The transportation accident was related to rain storm activity in the area  |
| and the driver of a passenger vehicle, responsible for the accident,         |
| received a traffic citation for speed too fast for conditions. The tractor   |
| suffered minor damage, but once released by the South Carolina State Police  |
| was able to be driven approximately 6 miles to a repair facility. No damage  |
| was noted to the trailer, shipping cask, or cask tie down equipment at the   |
| accident scene                                                               |
|                                                                              |
| "At the repair facility, a mechanic evaluated the tractor condition and      |
| cleared the tractor and trailer for continued service to the Chem Nuclear    |
| Consolidation Facility in Barnwell, SC. The driver of the tractor performed  |
| a dose rate survey of the trailer and the dose rates were unchanged from the |
| measured values at the Fermi site.                                           |
|                                                                              |
| "Fermi 2 does not intend to submit a press release in Michigan since the     |
| accident occurred in South Carolina and the proper South Carolina agencies   |
| were notified.                                                               |
|                                                                              |
| "A follow up report is not anticipated, since no damage to the waste         |
| shipping cask was noted at the repair facility."                             |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38069       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 06/13/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 12:31[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        06/13/2001|
+------------------------------------------------+EVENT TIME:        08:39[CDT]|
| NRC NOTIFIED BY:  BRETT WELLER                 |LAST UPDATE DATE:  06/13/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ROGER LANKSBURY      R3      |
|10 CFR SECTION:                                 |                             |
|ACOM 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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PARTIAL LOSS OFFSITE COMMUNICATIONS                                          |
|                                                                              |
| On Wednesday, June 13th at 0839, a lightning strike caused a loss of the     |
| commercial phone systems at the Monticello Nuclear Plant Site.  This         |
| affected phones in the control room and Technical Support Center as well as  |
| plant paging capabilities.  One commercial phone line in the control room,   |
| the ENS system, auto-ring hotlines to the State EOC/Duty Officer, fax        |
| capabilities and the Radio System to Off-site agencies remained operational. |
| Notification to the State and Local Counties were made informing them of the |
| degraded communication capabilities.  The EOF phone system remained          |
| operational.  All communication systems were restored at approximately 1100  |
| on June 13th.                                                                |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38070       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 06/13/2001|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 20:12[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        06/13/2001|
+------------------------------------------------+EVENT TIME:        19:30[EDT]|
| NRC NOTIFIED BY:  ERIC OLSON                   |LAST UPDATE DATE:  06/13/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANIELLO DELLA GRECA  R1      |
|10 CFR SECTION:                                 |JOHN HICKEY          NMSS    |
|KSNM 70.52(a)            LOSS OF SNM/CRIT       |DAVID MATTHEWS       NRR     |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| A SMALL QUANTITY OF SPECIAL NUCLEAR MATERIAL UNACCOUNTED FOR                 |
|                                                                              |
| During the process of investigation of the Transverse In-Core Probe (TIP)    |
| detector accountability issue reported on 6/8/01 (EN 38059) it has been      |
| discovered that one additional detector cannot be readily accounted for.     |
| This was discovered during verification of the detectors installed in the    |
| TIP machines.  The TIP detector is a fission chamber that utilizes           |
| approximately 1 mg of enriched uranium and is therefore considered Special   |
| Nuclear Material (SNM).                                                      |
|                                                                              |
| During 1975 to 1986 Pilgrim did not track TIP detectors as SNM due to the    |
| detectors containing less than one gram of SNM.  It is suspected that during |
| this time frame this detector was changed out.  In 1987 a records search was |
| made but did not reveal maintenance performed on this detector.  It Is       |
| believed that this TIP detector has been properly disposed of as radioactive |
| waste and is not in the public domain.  Investigation is continuing.         |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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