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Event Notification Report for January 9, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/08/2001 - 01/09/2001

                              ** EVENT NUMBERS **

37653  37654  37655  37656  

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|General Information or Other                     |Event Number:   37653       |
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| REP ORG:  FLORIDA BUREAU OF RADIATION CONTROL  |NOTIFICATION DATE: 01/08/2001|
|LICENSEE:  FLORIDA DEPARTMENT OF TRANSPORTATION,|NOTIFICATION TIME: 10:14[EST]|
|    CITY:  FT. LAUDERDALE           REGION:  2  |EVENT DATE:        01/08/2001|
|  COUNTY:                            STATE:  FL |EVENT TIME:             [EST]|
|LICENSE#:  0109-1                AGREEMENT:  Y  |LAST UPDATE DATE:  01/08/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |STEPHEN CAHILL       R2      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHARLEY ADAMS                |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE                                |
|                                                                              |
| The following is taken from a faxed report:                                  |
|                                                                              |
| A Troxler gauge containing 8 mCi Cs-137 and 40 mCi Am-241:Be was stolen.     |
| The Ft. Lauderdale Police case number is 013072.                             |
|                                                                              |
| Florida DOT bright orange van parked at owners address was stolen sometime   |
| between 6 a.m. Sunday (7th) and 7 a.m. Monday (8th). A Troxler gauge was in  |
| a locked box in the van. The keys to the gauge were not in the van. The      |
| police have been notified.                                                   |
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|Power Reactor                                    |Event Number:   37654       |
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| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 01/08/2001|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 13:54[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/07/2001|
+------------------------------------------------+EVENT TIME:        09:30[EST]|
| NRC NOTIFIED BY:  GREGORY CIRAULA              |LAST UPDATE DATE:  01/08/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID LEW            R1      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| CLOSED FIRE DAMPERS WOULD RESULT IN BYPASS OF HEPA FILTERS                   |
|                                                                              |
| "On January 6, 2001, during testing of the auxiliary building ventilation    |
| system, it was noted that the flow through the HEPA-charcoal train did not   |
| meet the Technical Specification acceptance criterion. Upon further          |
| investigation by plant personnel on January 7, 2001 at 0930 it was           |
| discovered that fire damper ABF13 had closed. Closure of this damper         |
| resulted in the closure of damper ABS8 (an excess flow damper). On January   |
| 8, 2001, at 1030 following further engineering evaluation, it was determined |
| that with these dampers closed, filtration of the effluents from the pipe    |
| chase and RHR areas would not have been processed through the HEPA-charcoal  |
| absorber. This condition does not meet the assumptions of the Salem offsite  |
| dose analysis, and therefore the condition meets the reporting requirements  |
| of 10 CFR 50.72(b)(2)(iii). As of January 7, 2001 at 1605 dampers ABF13 and  |
| ABS8 were open and flow through the HEPA-charcoal train was verified to meet |
| Technical Specification acceptance criterion."                               |
|                                                                              |
| The NRC resident inspector will be informed of this report by the licensee.  |
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|Power Reactor                                    |Event Number:   37655       |
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| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 01/08/2001|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 16:32[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/08/2001|
+------------------------------------------------+EVENT TIME:        11:50[CST]|
| NRC NOTIFIED BY:  STEPHEN JOBE                 |LAST UPDATE DATE:  01/08/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DALE POWERS          R4      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| HPCI SYSTEM DECLARED INOPERABLE                                              |
|                                                                              |
| "The High Pressure Coolant Injection (HPCI) system was declared inoperable   |
| due to an air line leak. The unplanned loss of a single train system (such   |
| as HPCI) is reportable as a loss of safety function. The air line supplies   |
| air to air-operated valves for draining the steam supply line to ensure that |
| the HPCI steam supply line does not fill with water. Upon a HPCI initiation  |
| signal that would cause the steam supply valve to open or on a loss of air   |
| pressure, these air-operated valves automatically shut. With the degraded    |
| condition of the air supply line, assurance could not be maintained that the |
| steam lines would be maintained clear of water. HPCI is presently available  |
| and capable of injecting if required."                                       |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
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|Fuel Cycle Facility                              |Event Number:   37656       |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 01/08/2001|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 20:27[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        01/08/2001|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        11:27[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/08/2001|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JOHN JACOBSON        R3      |
|  DOCKET:  0707002                              |PATRICIA HOLAHAN     NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KURT SISLER                  |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| 24-HOUR NRC BULLETIN 91-01 REPORT                                            |
|                                                                              |
| "At 1127 hours, 01/08/01, the Plant Shift Superintendent's (PSS) office was  |
| notified of a discrepancy in the U-235 Mass log in room 229, X-710 Lab       |
| Services Facility. A NCS Anomalous Condition was initiated and NCS Engineer  |
| personnel were contacted to investigate the discrepancy. Investigation       |
| revealed that two containers were moved from room 229 into room 330 without  |
| being logged out of room 229 or logged into room 330. The failure to log the |
| movement of the two containers into and out of the respective mass           |
| inventories represents a loss of controls 2a and 2b of NCSA-0710_022.A01.    |
| Since the NCSE takes credit for these controls to satisfy both legs of the   |
| double contingency principle, this event involves the loss of both controls  |
| credited for double contingency. At 1430 hours, 01/08/01, NCS Engineering    |
| reported that compliance with NCSA-0710_022.A01 was reestablished This event |
| does not involve greater than a safe mass and moderation is not a control    |
| (primary or otherwise) in the affected NCSA/NCSE.                            |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:                                              |
|                                                                              |
| "The safety significance of this event is low. The U-235 mass inventory in   |
| Room 330 is 129.1 grams, which is well below the safe mass limit if 230      |
| grams of U-235 for oily material. The failure to log the container movement  |
| at no time challenged the safe mass limit. A minimum of 588 grams U-235      |
| (Reference POEF-LMUS-44) would be needed to support a criticality at the     |
| analyzed enrichment limit (100%) under optimum conditions                    |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW           |
| CRITICALITY COULD OCCUR):                                                    |
|                                                                              |
| "If the safe U-235 mass limit was at the maximum allowable value for         |
| operations involving oily material, and these two containers were added to   |
| the mass present, there would need to be an additional 347 grams of U-235    |
| present in the room before a critical mass for full reflection, optimum      |
| moderation and spherical geometry were exceeded for oily conditions. For     |
| this amount of U-235 to be present, multiple errors in the log book would    |
| need to occur.                                                               |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):    |
|                                                                              |
| "The control Parameter for this operation is mass. NCSA-0710_022 places two  |
| controls on this parameter. The combined mass of all fissile material is     |
| limited to 350 grams of U-235 for non-oily/greasy material and 230 grams of  |
| U-235 if oily/greasy material is present. The NCSA requires that a log of    |
| U-235 mass inventory be maintained to demonstrate that the mass limit is not |
| exceeded. Each log entry consists of the mass value plus analytical          |
| uncertainty. A log entry is made by the person responsible for the movement  |
| of U-235 into the room and is verified by a second knowledgeable person.     |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT. FORM OF LICENSED MATERIAL (INCLUDE PROCESS    |
| LIMIT AND % WORST CASE OF CRITICAL MASS):                                    |
|                                                                              |
| "There were approximately 100 containers in room 330 that contain 129.1      |
| grams of U-235 in both solid and liquid form. Out of these containers there  |
| were approximately 33.7 grams U-235 enriched to greater than 20% in fire     |
| room at the time of this event. The NCS analysis assumes 100% enrichment in  |
| developing the mass limit and does not control enrichment.                   |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES                                              |
|                                                                              |
| "Two containers with >500 ppm U-235 concentration and greater than 1.0       |
| weight percent U-235 enrichment were not logged out of room 229 nor were     |
| they logged into room 330. Since they were not logged in or out, no          |
| verification was performed. The safety significance of this event is low due |
| to the small amount of U-235 involved."                                      |
|                                                                              |
| The NRC resident inspector has been informed of this notification.           |
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