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Event Notification Report for September 16, 2002


                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/13/2002 - 09/16/2002

                              ** EVENT NUMBERS **

39142  39187  39188  39189  39190  39191  39192  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39142       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 08/21/2002|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 21:03[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        08/21/2002|
+------------------------------------------------+EVENT TIME:        14:00[CDT]|
| NRC NOTIFIED BY:  EURMAN HENSON                |LAST UPDATE DATE:  09/13/2002|
|  HQ OPS OFFICER:  MIKE NORRIS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |WILLIAM JOHNSON      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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION REGARDING RCS BORATION REQUIREMENTS                     |
|                                                                              |
| "On August 21, 2002, with Callaway Plant in Mode 1 at 100 % power, it was    |
| determined that a potential unanalyzed condition had existed regarding       |
| Reactor Coolant System (RCS) boration requirements when in Mode 3 below the  |
| P-11 setpoint of 1970 psig RCS pressure. During an extent of condition       |
| review, a concern had been identified regarding the Westinghouse analysis of |
| Steam Line Breaks in Mode 3 below P-11. In order to conclude that acceptable |
| core performance results would be obtained for a lower Mode 3 Steam Line     |
| Break, the Westinghouse analyses assumes that the plant is borated to cold   |
| shutdown conditions prior to blocking P-11. Discussions with Westinghouse    |
| confirmed this requirement was applicable to Callaway. Callaway Plant        |
| procedures did not specifically require that the plant be maintained at Cold |
| Shutdown boron concentrations with P-11 blocked. A historical review         |
| documented that the Callaway Plant shutdown twice within the last three      |
| years. During these shutdowns, the plant maneuvered through Mode 3 below     |
| P-11 once during each plant shutdown and once during each plant startup.     |
|                                                                              |
| "A review of historical data is being conducted for those periods to         |
| establish actual boron concentrations versus calculated requirements for     |
| past conditions. Preliminary reviews for three of those periods have been    |
| completed and document actual boron concentrations of 1397 ppm or greater.   |
|                                                                              |
| "This condition is being reported as an unanalyzed condition until           |
| historical reviews determine otherwise. Compensatory actions taken included  |
| determining a boron concentration that would satisfy accident analysis       |
| requirements for present plant conditions and revising Callaway Plant        |
| procedures to require boration to specified boron concentrations for Mode 3  |
| operation with P-11 blocked."                                                |
|                                                                              |
| P-11(Pressurizer SI Block Permissive) enables BLOCK switches to allow the    |
| operator to block low Pressurizer pressure SI.                               |
|                                                                              |
| The NRC Resident Inspector has been notified.  The Licensee has discussed    |
| this condition with Wolf Creek.                                              |
|                                                                              |
|                                                                              |
| ****RETRACTION ON 09/13/02 AT 1527ET BY E. HENSON TAKEN BY MACKINNON****     |
|                                                                              |
| Upon completion of a review of historical data encompassing the previous     |
| three years of plant operation, it was determined that sufficient boron      |
| concentrations were maintained to ensure compliance with accident analysis   |
| requirements when in Mode 3 below P-11. Based upon this information, no      |
| unanalyzed condition existed and Event Notification # 39142 is being         |
| retracted.  R4DO (Jack Whitten) notified.                                    |
|                                                                              |
| The NRC Resident Inspector was notified of this event retraction.            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39187       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 09/13/2002|
|    UNIT:  [1] [2] []                STATE:  TN |NOTIFICATION TIME: 07:45[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/13/2002|
+------------------------------------------------+EVENT TIME:        06:45[EDT]|
| NRC NOTIFIED BY:  TOM MARSHALL                 |LAST UPDATE DATE:  09/13/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |JON WALLO            R2      |
|10 CFR SECTION:                                 |JOHN DAVIDSON        TAT     |
|DDDD 73.71(b)(1)         SAFEGUARDS REPORTS     |WILLIAM RULAND       NRR     |
|                                                |JOSEPH HOLONICH      IRO     |
|                                                |AL MADISON           NSIR    |
|                                                |ANNE BOLAND          R2      |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| 1-HOUR SECURITY REPORT INVOLVING UNAUTHORIZED ENTRY INTO THE PROTECTED AREA  |
|                                                                              |
| Unauthorized entry into PA.  Immediate compensatory measures taken upon      |
| discovery,.  Licensee will inform the NRC Resident Inspector.  Contact the   |
| Headquarters Operations Officer for details.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39188       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 09/13/2002|
|    UNIT:  [1] [2] []                STATE:  TN |NOTIFICATION TIME: 09:35[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        09/13/2002|
+------------------------------------------------+EVENT TIME:        09:22[EDT]|
| NRC NOTIFIED BY:  TOM MARSHALL                 |LAST UPDATE DATE:  09/13/2002|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          UNUSUAL EVENT         |IRC                  R2      |
|10 CFR SECTION:                                 |TERRY REIS           EO      |
|AAEC 50.72(a) (1) (i)    EMERGENCY DECLARED     |JOSEPH HOLONICH      IRO     |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |DAVID BARDEN         FEMA    |
|                                                |DAMIEN               OHS     |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DECLARED BASED ON EMERGENCY DIRECTOR JUDGMENT                  |
|                                                                              |
| The licensee declared a UE at 0922 EDT based on the judgment of the          |
| Emergency Director and the previous physical security report EN #39187.  The |
| licensee commenced a search of all vital areas for explosives or other       |
| threats at 0900 EDT.  Also, an offsite notification to the FBI was made.     |
| The licensee informed the state and the NRC Resident Inspector.              |
|                                                                              |
| * * * UPDATED AT 2026 EDT ON 9/13/02 BY LARRY PRUETT TO FANGIE JONES * * *   |
|                                                                              |
| The licensee terminated the UE at 2002 EDT after completing a thorough       |
| search.  The licensee notified the NRC Resident Inspector and the state.     |
| Notified R2DO (Mike Ernstes), NRR EO (William Ruland), IRO (Joseph           |
| Holonich), NSIR (Roy Zimmerman), FEMA (Cibock), and OHS (Brahm).             |
|                                                                              |
| The NRC entered Monitoring for this event at 0855 EDT and exited at 2045     |
| EDT.                                                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39189       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 09/13/2002|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 15:03[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        09/13/2002|
+------------------------------------------------+EVENT TIME:        14:16[EDT]|
| NRC NOTIFIED BY:  R. STRICKLAND                |LAST UPDATE DATE:  09/13/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID LEW            R1      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| Contract guard accidentally discharged a  weapon in the protected area.      |
| Immediate compensatory measures were taken upon discovery.                   |
|                                                                              |
| NRC Resident Inspector will be notified by the licensee of this event.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   39190       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 09/13/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 20:15[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        09/12/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        21:20[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  09/13/2002|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |CHRISTINE LIPA       R3      |
|  DOCKET:  0707001                              |JANET SCHLUETER      NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  S. SKAGGS                    |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF ONE BARRIER OF DOUBLE CONTINGENCY                                    |
|                                                                              |
| NRC BULLETIN 91-01 24 HOUR NOTIFICATION                                      |
|                                                                              |
| At 2120 CDT, on 9-12-02 the Plant Shift Superintendent (PSS) was notified of |
| the following:                                                               |
| The C-337A south crane does not meet the intent of NUREG-0554 as required by |
| NCSA 042 SRI 5.5.6, NUREG 0554 section 6.3 requires the crane to have        |
| malfunction protection which should include controls to sense and respond to |
| conditions such as excessive electric current, excessive motor temperature,  |
| over speed, overload and over travel.  Over speed protection is not provided |
| in the event of a gearbox failure.  The NCSE/A requires that the crane meet  |
| specifications equivalent to NUREG-0554 when lifting cylinders over          |
| autoclaves that contain cylinders with liquid UF6 greater than or equal to   |
| 1.0 wt.% U235.                                                               |
| Following discovery, the use of this crane to move cylinders over liquid     |
| cylinders that contain equal to/greater than 1.0 wt.% U235 was suspended.    |
|                                                                              |
| The NRC Senior Resident Inspector has been notified of this event.           |
|                                                                              |
| SAFETY SIGNIFICANCE OF EVENTS:                                               |
|                                                                              |
| The crane used to move cylinders over liquid UF6 cylinders did perform as    |
| intended and no cylinder was dropped.  Therefore, the process conditions     |
| were not lost.                                                               |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO(S) OF HOW            |
| CRITICALITY COULD OCCUR                                                      |
|                                                                              |
| In order for a criticality to be possible, a cylinder would have to be       |
| dropped on an autoclave that houses a liquid cylinder such that the liquid   |
| cylinder ruptured.  The rupture liquid cylinder contents would then have to  |
| be moderated sufficiently to support a criticality.                          |
|                                                                              |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.)      |
|                                                                              |
| Double contingency for lifting cylinders over liquid cylinders located in    |
| autoclaves is maintained by requiring the crane to be single-failure proof.  |
| Therefore, in the event part of the crane fails, a second design feature     |
| would prevent the cylinder from falling onto an autoclave, rupturing         |
| rupturing a cylinder, and releasing liquid UF6 into the autoclave, which may |
| contain water and/or steam.  The integrity of the cylinder is intended to    |
| prevent moderation of the UF6 when placed in the autoclave.  Therefore       |
| dropping a cylinder onto an autoclave containing a liquid UF6 cylinder could |
| cause a criticality by allowing water or steam(I.e. moderator) to react with |
| UF6.                                                                         |
|                                                                              |
| The first leg of double contingency is based on the unlikely event of        |
| dropping a cylinder from an overhead bridge crane that has been designed to  |
| lift cylinders.  Since the overhead bridge crane that was used has a 20-ton  |
| capacity and the proper slings and lifting fixtures were used, this leg of   |
| double contingency was maintained.                                           |
|                                                                              |
| The second leg of double contingency is based on using a single-failure      |
| proof crane to move cylinders over liquid cylinders that contain greater     |
| than or equal to 1.0 wt% U235.  Because the crane is not single-failure      |
| proof meeting the requirements equivalent to NUREG-0554, this leg of double  |
| contingency was not maintained.                                              |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS     |
| LIMIT AND % WORST CASE CRITICAL MASS):                                       |
|                                                                              |
| 10 ton liquid UF6 Cylinder with a net weight of 20750 lbs UF6 enriched to    |
| ---- wt.% U235.                                                              |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |
| OF THE FAILURES OR DEFICIENCIES                                              |
|                                                                              |
| Crane was determined not to be single fail-proof as per applicable NCSE and  |
| NCSA requirements.                                                           |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED:  |
|                                                                              |
| Further use of this crane to move cylinders over liquid that contain greater |
| than or equal to 1.0 wt% U235 was immediately suspended and procedure        |
| changes initiated to reflect requirement.                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39191       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 09/14/2002|
|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 22:14[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        09/14/2002|
+------------------------------------------------+EVENT TIME:        20:12[EDT]|
| NRC NOTIFIED BY:  JOHNSTONE                    |LAST UPDATE DATE:  09/14/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |MIKE ERNSTES         R2      |
|10 CFR SECTION:                                 |                             |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BORIC ACID RESIDUE DISCOVERED DURING A BAREHEAD INSPECTION OF THE REACTOR    |
| VESSEL HEAD                                                                  |
|                                                                              |
| Two reactor vessel head penetrations on Unit 2 ( #21 and # 31) appear to     |
| have exhibited some amount of leakage during the past cycle of operation.    |
| This conclusion is based on the boric acid residue found at these locations  |
| during the barehead inspection.  This is a preliminary finding, further NDE  |
| and Liquid Penetrant Inspections will be preformed and a repair plan will be |
| developed during this outage.                                                |
|                                                                              |
| A inspection of the reactor vessel head was performed last year and no boric |
| acid residue was noted.                                                      |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   39192       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 09/15/2002|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 18:08[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        09/15/2002|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        14:00[CDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  09/15/2002|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |CHRISTINE LIPA       R3      |
|  DOCKET:  0707001                              |JANET SCHLUETER      NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  F. CAGE                      |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 4 HOUR NOTIFICATION                                       |
|                                                                              |
| At 0845 CDT, On 9-15-02 the Plant Shift Superintendent (PSS) was notified of |
| the following:                                                               |
|                                                                              |
| At approximately 0500 CDT, on 9-15-02 the Front Line Manager in the C-337    |
| Building observed the pressure in the Unit 3 Cell 2 Freezer-Sublimer (F/S)   |
| vessel to be above the required pressure level.  NCSA CAS-001                |
| Freezer-Sublimers at the Paducah Gaseous Diffusion Plant, requires the       |
| system pressure be maintained below a certain level and, If exceeded,        |
| immediate actions must be taken to reduce the system pressure.  Pressure was |
| not immediately restored to below NCS pressure limits.  At 0923 CDT on       |
| 9-15-02. the pressure was reduced to below the required limit.               |
|                                                                              |
| The NRC Senior Resident inspector has been notified of this event,           |
+------------------------------------------------------------------------------+