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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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, |
+------------------------------------------------------------------------------+
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