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Event Notification Report for August 7, 2002

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           08/06/2002 - 08/07/2002

                              ** EVENT NUMBERS **

39090  39111  39112  39114  
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|General Information or Other                     |Event Number:   39090       |
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| REP ORG:  MISSISSIPPI DIV OF RAD HEALTH        |NOTIFICATION DATE: 07/25/2002|
|LICENSEE:  BURNS, COOLEY AND DENNIS, INC        |NOTIFICATION TIME: 11:30[EDT]|
|    CITY:  JACKSON                  REGION:  2  |EVENT DATE:        07/24/2002|
|  COUNTY:                            STATE:  MS |EVENT TIME:             [CDT]|
|LICENSE#:  MS61901               AGREEMENT:  Y  |LAST UPDATE DATE:  08/06/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MARK LESSER          R2      |
|                                                |JOHN HICKEY          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOSH GRISHAM                 |                             |
|  HQ OPS OFFICER:  MIKE NORRIS                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER GAUGE                      |
|                                                                              |
| A Troxler gauge model 3440, serial number 31621, was stolen out of the bed   |
| of a truck in front of a private residence.  The vehicle was parked at 2300  |
| on 7/24/02 and the gauge was found missing at 0700 on 7/25/02.   The gauge   |
| contains 8 millicuries of Cs-137 and 40 millicuries of Am-241:Be.  Local law |
| enforcement has notified and a press release is planned for the local        |
| newspaper.                                                                   |
|                                                                              |
| * * * UPDATED AT 1220 EDT ON 8/6/02 BY JOSH GRISHAM TO FANGIE JONES * * *    |
|                                                                              |
| The gauge has been recovered in good condition.                              |
|                                                                              |
| Notified R2DO (Caudle Julian) and NMSS EO (Charlie Miller).                  |
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|Power Reactor                                    |Event Number:   39111       |
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| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 08/06/2002|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 04:34[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        08/05/2002|
+------------------------------------------------+EVENT TIME:        23:33[CDT]|
| NRC NOTIFIED BY:  BRIAN HUPKE                  |LAST UPDATE DATE:  08/06/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       94       Power Operation  |94       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| LOSS OF RESIDUAL HEAT REMOVAL (RHR)  HEAT REMOVAL CAPABILITY.                |
|                                                                              |
| "At 23:33 on 8/5/02 both loops of RHRSW (Residual Heat Removal Service       |
| Water) were declared inoperable due to experiencing high differential        |
| pressure greater than 12 psid across the 'A' loop RHRSW strainer and the 'B' |
| loop RHRSW strainer.                                                         |
|                                                                              |
| "On 8/4/02 while running a surveillance for the 'B' RHRSW pump a high        |
| strainer differential pressure annunciator was received, which comes in a 6  |
| psid.  'B' pump flow at the time was 2400 GPM.  The in plant operator was    |
| sent locally to investigate the local differential pressure indication and   |
| discovered the instrument was pegged high at > (greater than ) 15 psid.  The |
| pump was secured and the corresponding Limiting Condition of Operation of 7  |
| days was entered for the 'B' RHRSW loop.  Maintenance was immediately        |
| planned and begun to clean the 'B' RHRSW strainer.  At the time plans were   |
| also made to inspect the 'B' RHRSW/ESW (Emergency Service Water) pit and     |
| Stilling Basin.                                                              |
|                                                                              |
| "On 8/5/02 after inspections of the Stilling basin found algae growth, plans |
| were made to run the 'A' side RHRSW pumps to determine operability of the    |
| 'A' loop of RHRSW.  At that time the Stilling basin cleaning also began.     |
| After the completion of stilling basin cleaning on 8/5/02, the 'A' RHRSW     |
| pump was started and strainer differential was between 2.5 - 4.5 psid at a   |
| pump flow of 2400 GPM which was held for 15 minutes.  At this time the 'C'   |
| RHRSW pump was started and flow raised to 4100 GPM at which time strainer    |
| differential pressure was steady at 5.5 - 6.0 psid.  As flow was raised to   |
| 5000 GPM Strainer differential pressure pegged high at > (greater than) 15   |
| psid within 3 minutes.  The 'A' RHRSW pump was then secured and flow lowered |
| to 2100 GPM where strainer differential pressure remained at 10 - 12 psid    |
| and then pegged high at greater than 15 psid.  The 'C' RHRSW pump was then   |
| secured and the 'A' RHRSW loop was declared inoperable at 23:33 on 8/5/02.   |
| The LCO for both loops of RHRSW inoperable was then entered at 23:33 on      |
| 8/5/02.                                                                      |
|                                                                              |
| "This report is being made under 50.72(b)(3)(v)(B) 'Any event or condition   |
| that at the time of discovery could have prevented the fulfillment of the    |
| safety function of structures or systems that are needed to remove residual  |
| heat.' "                                                                     |
|                                                                              |
|                                                                              |
| All other Emergency Core Cooling Systems are fully operable if needed.       |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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|Power Reactor                                    |Event Number:   39112       |
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| FACILITY: DUANE ARNOLD             REGION:  3  |NOTIFICATION DATE: 08/06/2002|
|    UNIT:  [1] [] []                 STATE:  IA |NOTIFICATION TIME: 10:16[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        08/06/2002|
+------------------------------------------------+EVENT TIME:        07:53[CDT]|
| NRC NOTIFIED BY:  DAVID MANKIN                 |LAST UPDATE DATE:  08/06/2002|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |BRENT CLAYTON        R3      |
|10 CFR SECTION:                                 |BOB DENNING          NRR     |
|ASHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |TIM MCGINTY          DIRO    |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE  
|
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       94       Power Operation  |62       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO BOTH RESIDUAL HEAT
REMOVAL  |
| SERVICE WATER SUBSYSTEMS BEING DECLARED INOPERABLE.                          |
|                                                                              |
|                                                                              |
| "Initiated plant shutdown in accordance with Tech Spec 3.7.1, Required       |
| Action E.1 due to required actions and associated completion times not meet  |
| (met) for both Residual Heat Removal Service Water subsystems being          |
| inoperable.  Per Tech Specs, plant is required to be in Mode 3 by 1933 hours |
| today (8/6/2002) and in Mode 4 by 1933 hours on 8/7/2002. Plant shutdown was |
| commenced at 0753 hours today.                                               |
|                                                                              |
| "This report is being made under 50.72(b)(2)(I), 'The initiation of any      |
| nuclear plant shutdown required by plant's Technical Specifications."        |
|                                                                              |
| All Emergency Core Cooling Systems and the Emergency Diesel Generators are   |
| fully operable if needed.  The electrical grid is stable.   The licensee     |
| will reduce reactor power down to between 10 to 15 percent power then        |
| manually scram the reactor.                                                  |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| See event # 39111 for background information.                                |
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|Power Reactor                                    |Event Number:   39114       |
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| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 08/06/2002|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 16:08[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        08/06/2002|
+------------------------------------------------+EVENT TIME:        10:00[CDT]|
| NRC NOTIFIED BY:  STEVE GIFFORD                |LAST UPDATE DATE:  08/06/2002|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |CHUCK CAIN           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  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| LICENSEE DISCOVERED A POST-FIRE SAFE SHUTDOWN FUNCTION THAT MAY NOT
BE MET   |
|                                                                              |
| "On August 6, 2002, conditions were discovered where a postulated fire could |
| cause the pressurizer to blow down to the pressurizer relief tank (PRT).     |
| Wolf Creek is in Mode 1, at 100% power.                                      |
|                                                                              |
| "During reviews associated with post-fire safe shutdown reanalysis work,     |
| Wolf Creek personnel discovered that power and control cables for a          |
| pressurizer power operated relief valve (PORV) and its associated motor      |
| operated block valve are routed in electrical raceways with no horizontal    |
| separation. The two valves are in the same electrical separation group but   |
| are redundant in their post-fire safe shutdown function to prevent reactor   |
| coolant system (RCS) blowdown to the PRT. Further investigation determined   |
| that the power and control cables in the opposite separation group have the  |
| same configuration. This does not meet our commitments to 10 CFR 50 Appendix |
| R.lll.G as reflected in our approved Fire Protection Plan.                   |
|                                                                              |
| "During a fire in the plant, it is the function of PORV valves and block     |
| valves to provide a barrier to blowing down the RCS into the PRT. A fire in  |
| any of the affected fire areas in which the circuits are routed has the      |
| potential to damage cables in a manner that cause a the PORV to spuriously   |
| open (due to a hot short), and to damage cables in a manner that causes the  |
| block valve to not respond to a close signal (due to an open circuit or a    |
| hot short). This would cause a non-isolable RCS blowdown to the PRT.         |
|                                                                              |
| "Based on the guidance provided in NUREG 1022 Revision 2, this situation     |
| meets the criterion of 10 CFR 50.72(b)(3)(ii)(B) for an 8-hour ENS           |
| notification, as it relates to being in an unanalyzed condition.             |
|                                                                              |
| "The licensee has implemented a 1-hour fire watch and is developing          |
| compensatory measures.                                                       |
|                                                                              |
| "The licensee notified the NRC Resident Inspector."                          |
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