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). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|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
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| - 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 |
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| 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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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021