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Event Notification Report for March 23, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/22/2000 - 03/23/2000

                              ** EVENT NUMBERS **

36788  36803  36823  36824  

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|Power Reactor                                    |Event Number:   36788       |
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| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 03/11/2000|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 16:07[EST]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        03/11/2000|
+------------------------------------------------+EVENT TIME:        14:30[EST]|
| NRC NOTIFIED BY:  DEAL                         |LAST UPDATE DATE:  03/22/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |EDWARD MCALPINE      R2      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| DEFECT DETECTED DURING EDDY CURRENT INSPECTION OF STEAM GENERATOR            |
|                                                                              |
| "Turkey Point is performing eddy current testing of the Unit 3 steam         |
| generators in accordance with Plant Technical Specifications and Industry    |
| Guidance. A 20% inspection was planned for the top of tubesheet expansion    |
| transition region in the hot leg of each steam generator. This total planned |
| sample was divided into 1st, 2nd and 3rd samples to address the progressive  |
| inspection process of the Technical Specifications Table 4.4-2. The 1st      |
| sample of 96 tubes in the 3B steam generator resulted in detection of 1      |
| defect near the top of the tubesheet. In accordance with Technical           |
| Specification 4.4.5.5c, this defect results in a C-3 Classification for the  |
| 1st sample.                                                                  |
|                                                                              |
| "A small number of additional indications near the top of the tubesheet have |
| also been detected in this steam generator, and the inspection is ongoing.   |
| The inspection will be expanded to 100% of the tubes in the 3B steam         |
| generator.                                                                   |
|                                                                              |
| "Eddy current results indicate the defects are shallow volumetric or         |
| pit-like in nature. A preliminary structural evaluation indicates that all   |
| indications detected to date meet the structural and leakage integrity       |
| performance criteria of NEI 97-06, 'Steam Generator Program Guidelines.'"    |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
|                                                                              |
| * * * UPDATE 1537 3/22/2000 FROM MOWREY TAKEN BY STRANSKY * * *              |
|                                                                              |
| "The steam generator inspection effort at Turkey Point Unit 3 was completed  |
| on March 16, 2000. The scope of inspection was expanded to 100% of the hot   |
| leg top of tubesheet for all three steam generators. Scope expansion for the |
| 3B steam generator was driven by Technical Specification requirements. Scope |
| expansion for the 3A steam generator was driven by the performance criteria  |
| contained in NEI 97-06, 'Steam Generator Program Guidelines.' Scope          |
| expansion in the 3C steam generator was pursued as a prudent measure due to  |
| the results in the 3A and 3B steam generators.                               |
|                                                                              |
| "The total number of tubes plugged during this inspection were as follows:   |
|                                                                              |
| "3A SG: 7 tubes for ID circumferential indications, 3 tubes for OD           |
| circumferential indications, 13 tubes for OD volumetric indications and 2    |
| tubes for wear indications. Total of 25 tubes plugged.                       |
|                                                                              |
| "3B SG: 2 tubes for ID circumferential indications, 3 tubes for OD           |
| circumferential indications, 22 tubes for OD volumetric indications and 1    |
| wear indications. Total of 28 tubes plugged.                                 |
|                                                                              |
| "3C SG: 6 tubes for ID circumferential indications, 2 tubes for OD           |
| circumferential indications, 6 tubes for OD volumetric indications and 2     |
| wear indications. Total of 16 tubes plugged.                                 |
|                                                                              |
| "An investigation has been conducted to determine the cause of the tube      |
| degradation identified during this inspection. This investigation included a |
| review of the steam generator design features, manufacturing information,    |
| inspection techniques, and historical and current chemistry programs. Due to |
| the lack of prior inspection data, and the limited number of defects         |
| identified by the industry for thermally treated alloy 600 tubing, the       |
| results are inconclusive for the circumferential and volumetric indications. |
| The potential causes for these mechanisms are suspected to be original       |
| manufacturing anomalies, inspection anomalies, or corrosion attack. The      |
| number of indications found is attributed to an inspection transient         |
| resulting from first time extended use of rotating probe technology at       |
| Turkey Point.                                                                |
|                                                                              |
| "The corrective measures taken to prevent recurrence of the potential causes |
| of degradation are as follows:                                               |
|                                                                              |
| "*   The inspection was expanded to cover 100% of the hot leg areas affected |
| by the circumferential and volumetric indications in order to provide a      |
| complete baseline with the rotating probe technology.                        |
|                                                                              |
| "*   The chemistry program is continually reviewed for enhancement           |
| opportunities and compliance with the latest industry guidance. Turkey Point |
| has initiated the addition of ethanolamine (ETA) to reduce iron transport to |
| the steam generators.                                                        |
|                                                                              |
| "*   Aggressive sludge removal techniques have been incorporated including   |
| high volume bundle flushing.                                                 |
|                                                                              |
| "*   The latest industry inspection guidelines will continue to be           |
| implemented, to ensure adequate inspections are conducted.                   |
|                                                                              |
| "Mechanical wear indications have been tracked for Turkey Point Unit 3 since |
| the fourth cycle of operation for the current steam generators (1990). The   |
| cause of this type of degradation is a well understood design issue. Tubes   |
| with wear indications were plugged based on qualified sizing techniques.     |
| Tubes plugged for mechanical wear were not the cause of the 10CFR50.72       |
| notification."                                                               |
|                                                                              |
| The NRC resident inspector has been informed of this update by the licensee. |
| Notified R2DO (Decker).                                                      |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36803       |
+------------------------------------------------------------------------------+
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| FACILITY: GRAND GULF               REGION:  4  |NOTIFICATION DATE: 03/16/2000|
|    UNIT:  [1] [] []                 STATE:  MS |NOTIFICATION TIME: 15:22[EST]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        03/15/2000|
+------------------------------------------------+EVENT TIME:        02:15[CST]|
| NRC NOTIFIED BY:  MARTY McADORY                |LAST UPDATE DATE:  03/22/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KRISS KENNEDY        R4      |
|10 CFR SECTION:                                 |                             |
|HFIT 26.73               FITNESS FOR DUTY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 SUPERVISOR ARRESTED AND CHARGED WITH FELONY POSSESSION OF A         |
| CONTROLLED SUTSTANCE                                                         |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[At 0215 CST on 03/15/00, a] licensee supervisor was arrested and charged   |
| with felony possession of a controlled substance.  The individual's          |
| unescorted access was immediately revoked upon discovery of the event [at]   |
| 1510 [CST] on [03/15/00].  A licensee investigation has been initiated to    |
| obtain additional details related to this off-site event."                   |
|                                                                              |
| "The NRC [resident inspectors] and licensee senior management [have] been    |
| informed."                                                                   |
|                                                                              |
| Call the NRC operations officer for additional details.                      |
|                                                                              |
| * * * UPDATE 1714 3/22/2000 FROM DAVID HANKS TAKEN BY BOB STRANSKY * * *     |
|                                                                              |
| The individual tested positive for drug use after being administered a       |
| for-cause test by the licensee following the arrest. The individual's        |
| unescorted access remains suspended. The licensee is currently reviewing     |
| work performed by this individual. The NRC resident inspector has been       |
| informed of this update by the licensee.                                     |
|                                                                              |
| Notified R4DO (Yandell).                                                     |
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|Power Reactor                                    |Event Number:   36823       |
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| FACILITY: NINE MILE POINT          REGION:  1  |NOTIFICATION DATE: 03/22/2000|
|    UNIT:  [] [2] []                 STATE:  NY |NOTIFICATION TIME: 00:48[EST]|
|   RXTYPE: [1] GE-2,[2] GE-5                    |EVENT DATE:        03/21/2000|
+------------------------------------------------+EVENT TIME:        21:36[EST]|
| NRC NOTIFIED BY:  STEVE FREGEAU                |LAST UPDATE DATE:  03/22/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LOUIS MANNING        R1      |
|10 CFR SECTION:                                 |                             |
|AESF 50.72(b)(2)(ii)     ESF ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - SERVICE WATER SYSTEM NONESSENTIAL VALVES ISOLATED DURING MAINTENANCE       |
| ACTIVITIES -                                                                 |
|                                                                              |
| During performance of preplanned Division I Service Water System (SWS) logic |
| circuitry relay replacement activities, an installed electrical jumper       |
| failed to maintain contact within the circuit causing a fuse to blow and the |
| subsequent automatic isolation of the Division II SWS nonessential valves.   |
| This potential failure had been discussed in preevaluation briefings as a    |
| distinct possibility and a contingency was in place.                         |
|                                                                              |
| Maintenance technicians replaced the fuse and restored flow to the           |
| nonessential headers.                                                        |
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+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36824       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  KANSAS DEPT OF HEALTH & ENVIRONMENT  |NOTIFICATION DATE: 03/22/2000|
|LICENSEE:  MT. CARMEL MEDICAL CENTER            |NOTIFICATION TIME: 15:07[EST]|
|    CITY:  PITTSBURG                REGION:  4  |EVENT DATE:        03/22/2000|
|  COUNTY:                            STATE:  KS |EVENT TIME:             [CST]|
|LICENSE#:  19-C243-01            AGREEMENT:  Y  |LAST UPDATE DATE:  03/22/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |LAWRENCE YANDELL     R4      |
|                                                |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  THOMAS CONLEY                |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| "During a routine license inspection it was noted a fluoroscopy technologist |
| had received a reported film badge exposure of approximately 8 rem during    |
| 1999. It was also noted this same individual had an exposure reported during |
| one month of 1999 exceeding 116 rem. A subsequent evaluation by the licensee |
| and the dosimetry processor indicated the 116 rem exposure was probably an   |
| anomaly and therefore was taken off the individual's exposure record. This   |
| was based on a review of past exposures and a review of the film which       |
| showed no discernable filter patterns.                                       |
|                                                                              |
| "The annual exposure of approximately 8 rem is currently unexplained and is  |
| being investigated by the licensee. The licensee requested the individual be |
| given blood tests to confirm the potential exposure. The individual refused  |
| the blood tests.                                                             |
|                                                                              |
| "Neither of these exposures reported to the licensee by the dosimetry        |
| processor was reported to the State Radiation Control Program as required."  |
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