The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37933       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   38066       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.                                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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.                            |
+------------------------------------------------------------------------------+


Page Last Reviewed/Updated Thursday, March 25, 2021