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Event Notification Report for October 1, 2002



                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/30/2002 - 10/01/2002

                              ** EVENT NUMBERS **

39217  39231  39232  39233  

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|General Information or Other                     |Event Number:   39217       |
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| REP ORG:  CALIFORNIA RADIATION CONTROL PRGM    |NOTIFICATION DATE: 09/26/2002|
|LICENSEE:  CONSTRUCTION TESTING AND ENGINEERING,|NOTIFICATION TIME: 00:26[EDT]|
|    CITY:                           REGION:  4  |EVENT DATE:        09/24/2002|
|  COUNTY:                            STATE:  CA |EVENT TIME:        07:30[PDT]|
|LICENSE#:  CA 5309-37            AGREEMENT:  Y  |LAST UPDATE DATE:  09/26/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN PELLET          R4      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ROBERT GREGER                |                             |
|  HQ OPS OFFICER:  GERRY WAIG                   |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| STOLEN AND RECOVERED MOISTURE DENSITY GAUGE                                  |
|                                                                              |
| "The facility [Construction Testing and Engineering, Inc.] reported a stolen |
| gauge this morning and within an hour called back to report that the gauge   |
| had been recovered [by police].                                              |
|                                                                              |
| "The gauge had been picked up from the storage location around 4:30 AM that  |
| morning and was transported by the user to his home. The gauge remained      |
| locked by chain in the vehicle. When the user returned to his vehicle        |
| between 7:30 - 8 AM he discovered the chain had been cut and the case with   |
| the gauge was missing. He contacted the police and the Alternate Radiation   |
| Safety Officer for his region."                                              |
|                                                                              |
| CA Rad Health Branch will follow-up with the licensee to obtain the make,    |
| model, and serial number of the stolen/recovered gauge and will forward that |
| information to the Headquarters Operations Officer.                          |
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|Power Reactor                                    |Event Number:   39231       |
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| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 09/30/2002|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 11:05[EDT]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        09/29/2002|
+------------------------------------------------+EVENT TIME:        19:04[EDT]|
| NRC NOTIFIED BY:  BRIAN WEAVER                 |LAST UPDATE DATE:  09/30/2002|
|  HQ OPS OFFICER:  GERRY WAIG                   +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GLENN MEYER          R1      |
|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  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| LOSS OF CONTROL ROOM FILTRATION SYSTEM FUNCTION                              |
|                                                                              |
| "This report is being made due to a loss of function of the Control Room     |
| Envelope Filtration (CREF) system. On 9/29/2002 @ 20:05 Hrs., an operator on |
| rounds identified that control room envelope boundary door #288-1 was open   |
| instead of closed as expected. The door was found to be hung up open due to  |
| interference between the bottom door seal and the door stop. The operator    |
| closed the door upon discovery. This door is controlled with a key card      |
| reader however it can also be opened from both sides with a thumb latch as   |
| it is not a security vital door. An initial investigation using the security |
| computer revealed that the Fire Chief accessed the door at 19:04:26 Hrs.     |
| during daily door checks and checked it shut at that time. The next card     |
| reader activity was at 20:04:50 Hrs. by the operator on rounds who           |
| discovered the door open. With the door having been open for other than      |
| normal entry/exit, a loss of the control room envelope boundary existed. The |
| control room envelope boundary is required for CREF operability and          |
| function.  As a result, both subsystems of the CREF system were declared     |
| inoperable on 9/29/2002 @ 19:04 Hrs. in accordance with Technical            |
| Specification LCO 3.7.2 Condition A, Action A.1 and Condition B, Action B.   |
| I. Both CREF subsystems were restored to operable and applicable Conditions  |
| and Actions exited on 9/29/2002 @ 20:05 Hrs when the door was closed. LCO    |
| completion times were not exceeded. Deviation/Event Report (DER)             |
| NM-2002-4233 was written for event followup and Action Request (ACR)         |
| 02-04252 was written to correct the problem with the door hanging up on the  |
| door stop. After contacting supporting organizations to determine the        |
| reportability of the loss of the control room envelope boundary, this event  |
| was determined to be reportable in accordance with 10CFR50.72(b)(3)(v)(D)."  |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
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|General Information or Other                     |Event Number:   39232       |
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| REP ORG:  GENERAL ELECTRIC COMPANY             |NOTIFICATION DATE: 09/30/2002|
|LICENSEE:  GENERAL ELECTRIC COMPANY             |NOTIFICATION TIME: 17:06[EDT]|
|    CITY:  SAN JOSE                 REGION:  4  |EVENT DATE:        09/30/2002|
|  COUNTY:                            STATE:  CA |EVENT TIME:             [PDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  09/30/2002|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GLENN MEYER          R1      |
|                                                |VERN HODGE           NRR     |
+------------------------------------------------+JAY HENSON           R2      |
| NRC NOTIFIED BY:  JASON S. POST (fax)          |SONIA BURGESS        R3      |
|  HQ OPS OFFICER:  MIKE NORRIS                  |KRISS KENNEDY        R4      |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| PART 21.21 REPORT REGARDING MAIN STEAM ISOLATION VALVE OUT OF SERVICE        |
|                                                                              |
| "This letter provides final notification of a Reportable Condition under     |
| 10CFR 21.21(d), as committed in the Reference letter. It was previously      |
| submitted as a Reportable Condition for Brunswick Units 1 & 2 and as a 60    |
| Day Interim Report per 21.21 (a)(2) for other plants that may be determined |
| to be affected.                                                              |
|                                                                              |
| "The evaluation has been completed and it has been determined that in        |
| addition to Brunswick 1 & 2, this is a Reportable Condition for Duane        |
| Arnold, FitzPatrick, Hatch 2, Nine Mile Point 2, Perry 1 and Pilgrim. The    |
| basis for this conclusion is that GE Nuclear Energy (GE) analyses for these  |
| plants to justify operation at greater than 75% of rated power with one Main |
| Steam line Isolation Valve (MSIV) Out of Service (OOS) (i.e., one steam line |
| isolated) did not adequately address the long term impact of increased flow  |
| induced vibration on the remaining open MSIVs. Without a supporting bases,   |
| it cannot be assured that the open MSIVs would be able to perform their      |
| required safety function following extended operation at greater than 75% of |
| current rated power with one steam line isolated. This could possibly result |
| in offsite doses in excess of 10CFR 100.11 limits.                           |
|                                                                              |
| "The actual impact of this condition would only be of concern if MSIV        |
| operability had not been demonstrated following extended plant operation at  |
| greater than 75% of current rated power with one MSIV OOS, or if a plant was |
| currently in extended operation at greater than 75% of rated power with one  |
| MSIV OOS.                                                                    |
|                                                                              |
| "All other plants which have an MSIV OOS analysis provided by GE were either |
| limited to 75% of rated power, or the impact of long term operation on the   |
| open MSIVs was adequately evaluated for the power level specified in the     |
| analysis.                                                                    |
|                                                                              |
| "(ii) Identification of the facility, the activity, or the basic component   |
| supplied for such facility or such activity within the United States which   |
| fails to comply or contains a defect:                                        |
|                                                                              |
| "The Main Steam Line Valve Out-of-Service analysis for:                      |
| Utility                                                                      |
| Plant Name                                                                   |
| Carolina Power & Light                                  Brunswick 1 and 2    |
| Nuclear Management Co.                            Duane Arnold               |
| Entergy Nuclear Northeast                           FitzPatrick, Pilgrim     |
| Southern Nuclear Operating Co.                Hatch 2                        |
| Constellation Nuclear                                     Nine Mile Point 2  |
| First Energy Nuclear Operating Co.           Perry 1                         |
|                                                                              |
| "(iii) Identification of the firm constructing the facility or supplying the |
| basic component which fails to comply or contains a defect:                  |
|                                                                              |
| "GE Nuclear Energy, San Jose, California                                     |
|                                                                              |
| "(iv) Nature of the defect or failure to comply and safety hazard which is   |
| created or could be created by such defect or failure to comply:             |
|                                                                              |
| "The MSIV OOS analysis performed by GE evaluated plant operation at greater  |
| than 75% of rated power with three active steam lines and one steam line     |
| isolated. The GE analysis for the affected plants did not address the effect |
| of potential long-term flow induced vibration degradation on the open MSIVs, |
| including the effect on the MSIV air operated controls. Without adequate     |
| justification, it cannot be assured that the open MSIVs would close          |
| following extended operation with one MSIV OOS at greater than 75% of        |
| current rated power.                                                         |
|                                                                              |
| "If it is postulated that the plant operated for an extended period in the   |
| MSIV OOS condition and then a main steam line break were to occur in one of  |
| the three operational steam lines, then there is the potential that MSIVs    |
| would not close to terminate the release from a steam line break either from |
| a common mode failure of both MSIVs, in the broken line, or failure of one   |
| MSIV due to the high flow induced vibration and the other MSIV as the design |
| basis single failure. This condition would result in an un-terminated        |
| release, which would exceed the existing 10 CFR 100 radiation release        |
| limits.                                                                      |
|                                                                              |
| "(v) The date on which the information of such defect or failure to comply   |
| was obtained:                                                                |
|                                                                              |
| "June 24, 2002                                                               |
|                                                                              |
| "(vi) In the case of a basic component which contains a defect or failure to |
| comply, the number and locations of all such components in use at, supplied  |
| for, or being supplied for one or more facilities or activities subject to   |
| the regulations in this part:                                                |
|                                                                              |
| "A defect has been confirmed to exist in analysis provided by GE for         |
| Brunswick 1 and 2, Duane Arnold, Fitzpatrick, Pilgrim, Hatch 2, Nine Mile    |
| Point 2, and Perry 1.                                                        |
|                                                                              |
| "(vii) The corrective action which has been, is being, or will be taken; the |
| name of the, individual or organization responsible for the action; and the  |
| length of time that has been or will be taken to complete the action (note,  |
| these are actions specifically associated with the identified Reportable     |
| Condition):                                                                  |
|                                                                              |
| "GE has communicated to the affected plants the 75% power limitation when    |
| operating with one MSIV OOS.                                                 |
|                                                                              |
| "GE has revised existing internal engineering and program processes to       |
| explicitly screen any limiting configurations/conditions for current and     |
| future MSIV OOS evaluations.                                                 |
|                                                                              |
| "(viii) Any advice related to the defect or failure to comply about the      |
| facility, activity, or basic component that has been, is being, or will be   |
| given to purchasers or licensees:                                            |
|                                                                              |
| "GE recommends limiting operation to 75% of current rated power when         |
| operating with one MSIV OOS, unless there is an adequate justification to    |
| support extended operation at a higher power level."                         |
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|Power Reactor                                    |Event Number:   39233       |
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| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 09/30/2002|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 23:17[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        09/30/2002|
+------------------------------------------------+EVENT TIME:        22:10[EDT]|
| NRC NOTIFIED BY:  ROBERT BOESCH                |LAST UPDATE DATE:  09/30/2002|
|  HQ OPS OFFICER:  MIKE NORRIS                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |GLENN MEYER          R1      |
|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     A/R        Y       70       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| AUTOMATIC REACTOR SCRAM ON MAIN TURBINE TRIP DUE TO LOW CONDENSER VACUUM     |
|                                                                              |
| "Susquehanna Unit 2 experienced a automatic reactor SCRAM on a Main Turbine  |
| trip due to low condenser vacuum. The unit experienced a momentary loss of   |
| 2D130 (120 V AC power). The loss caused the offgas system to isolate, a      |
| runback on the A Reactor Recirc Pump and a scoop tube lock on the B reactor  |
| Recirc Pump. Efforts to re-establish the offgas system were unsuccessful.    |
| Following the SCRAM, reactor water level dropped to approx. -0.2", and was   |
| recovered by the Feedwater System. The offgas system and Condenser vacuum    |
| were restored shortly after the SCRAM to maintain the condenser available    |
| for heat removal. There were no ECCS initiations and no challenges to        |
| containment.                                                                 |
|                                                                              |
| "This event is an Reactor Protection System (RPS) actuation when the reactor |
| is critical, and is reportable as a four hour ENS Notification under 10 CFR  |
| 50.72(b)(2)(iv)(B)."                                                         |
|                                                                              |
| The Licensee has notified the NRC Resident Inspector.                        |
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