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Re: Three "Oops" in the operational health physics



A little defensive, aren't we?



Bill





jenday1 wrote:



> I noticed that these were missed last week.  I think we should be concerned

> with the lack of regulatory oversight in operational and reactor heatlh

> physics, because individuals are not adequately assessing the risks.  Am I

> correct, Mr. Lipton?

> -- John

>

> John Jacobus, MS

> Certified Health Physicist

> 3050 Traymore Lane

> Bowie, MD 20715-2024

> jenday1@email.msn.com (H)

>                     U.S. Nuclear Regulatory Commission

>                               Operations Center

>

>                               Event Reports For

>                            09/07/2001 - 09/10/2001

>

>                               ** EVENT NUMBERS **

>

> 38268  38269  38270  38271

>

> +---------------------------------------------------------------------------

> ---+

> |Power Reactor                                    |Event Number:   38268

> |

> +---------------------------------------------------------------------------

> ---+

> +---------------------------------------------------------------------------

> ---+

> | FACILITY: COLUMBIA GENERATING STATIREGION:  4  |NOTIFICATION DATE:

> 09/07/2001|

> |    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME:

> 00:47[EDT]|

> |   RXTYPE: [2] GE-5                             |EVENT DATE:

> 09/06/2001|

> +------------------------------------------------+EVENT TIME:

> 17:38[PDT]|

> | NRC NOTIFIED BY:  WILLIAM BAKER                |LAST UPDATE DATE:

> 09/07/2001|

> |  HQ OPS OFFICER:  FANGIE JONES

> +-----------------------------+

> +------------------------------------------------+PERSON

> ORGANIZATION |

> |EMERGENCY CLASS:          NON EMERGENCY         |LINDA SMITH          R4

> |

> |10 CFR SECTION:                                 |

> |

> |AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |

> |

> |                                                |

> |

> |                                                |

> |

> |                                                |

> |

> +-----+----------+-------+--------+-----------------+--------+--------------

> ---+

> |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

> +---------------------------------------------------------------------------

> ---+

> | REACTOR CORE ISOLATION COOLING SYSTEM MADE INOPERABLE

> |

> |

> |

> | "Columbia Generating Station Reactor Core Isolation Cooing (RCIC) system

> has |

> | been isolated and made inoperable per Technical Specification 3.5.3 and

> |

> | unavailable due to manual closure of the RCIC turbine trip valve.  The

> |

> | manual closure of the RCIC turbine trip valve was required due to the loss

> |

> | of automatic trip capability of the turbine trip valve [due to a solenoid

> |

> | failure].  This loss of automatic trip capability under postulated

> |

> | conditions could cause a water hammer event significant enough to threaten

> |

> | primary containment.

> |

> |

> |

> | "The RCIC system is a single train system and is listed in plant

> procedures  |

> | as an Engineered Safety Feature (ESF).

> |

> |

> |

> | "The RCIC system will function automatically or manually to inject water

> |

> | into the RPV if manually returned to service."

> |

> |

> |

> | The licensee notified the NRC Resident Inspector.

> |

> +---------------------------------------------------------------------------

> ---+

>

> +---------------------------------------------------------------------------

> ---+

> |Power Reactor                                    |Event Number:   38269

> |

> +---------------------------------------------------------------------------

> ---+

> +---------------------------------------------------------------------------

> ---+

> | FACILITY: LASALLE                  REGION:  3  |NOTIFICATION DATE:

> 09/07/2001|

> |    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME:

> 03:30[EDT]|

> |   RXTYPE: [1] GE-5,[2] GE-5                    |EVENT DATE:

> 09/07/2001|

> +------------------------------------------------+EVENT TIME:

> 00:24[CDT]|

> | NRC NOTIFIED BY:  MICHAEL FITZPATRICK          |LAST UPDATE DATE:

> 09/07/2001|

> |  HQ OPS OFFICER:  FANGIE JONES

> +-----------------------------+

> +------------------------------------------------+PERSON

> ORGANIZATION |

> |EMERGENCY CLASS:          NON EMERGENCY         |MARK RING            R3

> |

> |10 CFR SECTION:                                 |

> |

> |ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|

> |

> |                                                |

> |

> |                                                |

> |

> |                                                |

> |

> +-----+----------+-------+--------+-----------------+--------+--------------

> ---+

> |UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE

> |

> +-----+----------+-------+--------+-----------------+--------+--------------

> ---+

> |                                                   |

> |

> |2     M/R        Y       72       Power Operation  |0        Hot Shutdown

> |

> |                                                   |

> |

> +---------------------------------------------------------------------------

> ---+

>                                    EVENT TEXT

> +---------------------------------------------------------------------------

> ---+

> | MANUAL REACTOR SCRAM DUE TO 2 LOW PRESSURE HEATER STRINGS ISOLATING

> |

> |

> |

> | The following is taken from a facsimile report:

> |

> |

> |

> | This report is being made per 10CFR50.72(b)(2)(iv)(B) RPS actuation

> (scram)  |

> | (4 hour notification for U-2).

> |

> |

> |

> | At 12:24 AM CDT, Friday 9/7/01, U-2 was manually scrammed. The initiating

> |

> | event was a loss of 2 of 3 Low Pressure Feedwater Heater Strings. A high

> |

> | level condition was initially received in the 21A Low Pressure Heater,

> which |

> | caused the Condensate System inlet and outlet isolation valves to the 2A

> Low |

> | Pressure Heater String to close. Subsequently, a high level condition was

> |

> | also received in the 21C Low Pressure Heater, which caused the Condensate

> |

> | System inlet and outlet isolation valves to the 2C Low Pressure Heater

> |

> | String to close. With a second Low Pressure Heater String isolated, Unit 2

> |

> | was manually scrammed in accordance with LaSalle Procedure LOA-HD-201,

> |

> | "Heater Drain System Trouble".

> |

> |

> |

> | All systems operated as designed. There were no ECCS actuations or Primary

> |

> | Containment isolations. The lowest Reactor level reached was minus 20

> inches |

> | (141 inches above the top of active fuel) and was recovered to normal

> level  |

> | using feedwater. Reactor pressure responded normally. No Safety Relief

> |

> | Valves actuated. All Control Rods fully inserted.

> |

> |

> |

> | The NRC Resident Inspector has been notified.

> |

> |

> |

> | The cause of the Low Pressure Heater String loss is being investigated at

> |

> | this time.

> |

> +---------------------------------------------------------------------------

> ---+

>

> +---------------------------------------------------------------------------

> ---+

> |General Information or Other                     |Event Number:   38271

> |

> +---------------------------------------------------------------------------

> ---+

> +---------------------------------------------------------------------------

> ---+

> | REP ORG:  NEW MEXICO RAD CONTROL PROGRAM       |NOTIFICATION DATE:

> 09/07/2001|

> |LICENSEE:  WESTERN TECHNOLOGIES                 |NOTIFICATION TIME:

> 18:31[EDT]|

> |    CITY:  CUBA                     REGION:  4  |EVENT DATE:

> 09/06/2001|

> |  COUNTY:                            STATE:  NM |EVENT TIME:

> 11:00[MDT]|

> |LICENSE#:  DM 244-29             AGREEMENT:  Y  |LAST UPDATE DATE:

> 09/07/2001|

> |  DOCKET:

> |+----------------------------+

> |                                                |PERSON

> ORGANIZATION |

> |                                                |LINDA SMITH          R4

> |

> |                                                |M. WAYNE HODGES      NMSS

> |

> +------------------------------------------------+

> |

> | NRC NOTIFIED BY:  SHERRY MILLER                |

> |

> |  HQ OPS OFFICER:  JOHN MacKINNON               |

> |

> +------------------------------------------------+

> |

> |EMERGENCY CLASS:          NON EMERGENCY         |

> |

> |10 CFR SECTION:                                 |

> |

> |NAGR                     AGREEMENT STATE        |

> |

> |                                                |

> |

> |                                                |

> |

> |                                                |

> |

> |                                                |

> |

> +---------------------------------------------------------------------------

> ---+

>

>                                    EVENT TEXT

> +---------------------------------------------------------------------------

> ---+

> | MISSING TROXLER DENSITY GAUGE.

> |

> |

> |

> |

> |

> | Western Technologies, out of Albuquerque, accidentally left a 3430 Troxler

> |

> | moisture density gauge at mile marker 49 on US highway 550.   The moisture

> |

> | density gauge was out of its transport case laying on the side of the

> |

> | highway when the it was left behind. The driver immediately, within an

> hour, |

> | returned to the location and discovered that the gauge was missing.  State

> |

> | of New Mexico has recommended to the licensee that they offer a reward for

> |

> | the missing gauge.

> |

> +---------------------------------------------------------------------------

> ---+

>

> ************************************************************************

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