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Event Notification Report for December 16, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           12/15/1999 - 12/16/1999

                              ** EVENT NUMBERS **

36460  36513  36514  36515  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   36460       |
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| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 11/24/1999|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 13:59[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        11/24/1999|
+------------------------------------------------+EVENT TIME:        12:32[EST]|
| NRC NOTIFIED BY:  DAVID JENKINS                |LAST UPDATE DATE:  12/15/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LEN WERT             R2      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| REACTOR CORE ISOLATION COOLING (RCIC) TURBINE TRIPPED ON HIGH EXHAUST        |
| PRESSURE DURING POST-MAINTENANCE TESTING.                                    |
|                                                                              |
| While rolling the turbine during post-maintenance testing of RCIC system for |
| Unit 2, the turbine tripped on high exhaust pressure.  The turbine trip is   |
| caused by either one of two instruments sensing a high turbine exhaust       |
| pressure (nominally 45 psi).  Turbine exhaust pressure was not noted to be   |
| abnormally high on the control room instrumentation during this evolution.   |
| The licensee entered Technical Specification 3.7, which requires that the    |
| licensee return the RCIC system to service within 14 days or to shut down    |
| the unit.  All emergency core cooling systems are fully operable.            |
| Maintenance and engineering personnel are investigating this problem with    |
| initial focus on the pressure sensing instrumentation.                       |
|                                                                              |
| The NRC resident inspector was notified of this event by the licensee.       |
|                                                                              |
| *************** UPDATE AT 0918 ON 12/15/99 FROM CHARLES ELBERFELD TO LEIGH   |
| TROCINE ***************                                                      |
|                                                                              |
| The licensee is retracting this event notification.  The following text is a |
| portion of a facsimile received from the licensee:                           |
|                                                                              |
| "On November 24, 1999, at 0918 hours, the Reactor Core Isolation Cooling     |
| (RCIC) system was declared inoperable for scheduled maintenance/testing,     |
| which was to include static and dynamic testing of two RCIC system           |
| motor-operated valves as well as quarterly system operability surveillance   |
| testing required by the plant's technical specifications.  The RCIC turbine  |
| was started and subsequently secured three times during the                  |
| maintenance/testing evolution."                                              |
|                                                                              |
| "At approximately 1232 hours, the RCIC turbine was started again, and this   |
| time the RCIC turbine high exhaust pressure annunciator came in accompanied  |
| by a RCIC turbine trip.  The RCIC system was considered to be inoperable for |
| reasons that originated from other than maintenance or testing.  Based on    |
| the information available at the time, the condition was assessed as         |
| reportable in accordance with 10 CFR 50.72(b)(2)(iii), and on November 24,   |
| 1999, at 1359 hours, notification was made to the NRC (Event No. 36460)."    |
|                                                                              |
| "This notification was made because RCIC, being a single train system, did   |
| not operate properly during maintenance testing of the system.  At the time  |
| the notification was made, the cause of the malfunction had not been         |
| determined.  To meet the 4-hour report time limit, the conservative decision |
| was made to report the event."                                               |
|                                                                              |
| "Subsequently, it has been determined that the malfunction of the RCIC       |
| system was due to a condition which was introduced by the                    |
| maintenance/testing activities.  After the RCIC system had been started and  |
| operated in a test mode numerous times, a RCIC turbine exhaust line check    |
| valve began to bind to the point that, during the turbine start, the valve   |
| binding resulted in a pressure spike in the exhaust line of sufficient       |
| magnitude to cause a RCIC turbine trip.  This condition was corrected and    |
| post-maintenance testing completed satisfactorily.  The RCIC system was      |
| declared operable, and LCO A2-99-2468 was cancelled at 1639 on November 29,  |
| 1999."                                                                       |
|                                                                              |
| "Based on the sequence, this event is not reportable in accordance with 10   |
| CFR 50.72 or 50.73.  NUREG-1022, Revision 1, provides clarification of the   |
| reporting requirements contained within 10 CFR 50.72 and 50.73.              |
| Specifically, in discussions associated with events that alone could prevent |
| fulfillment of a safety function, NUREG-1022, Revision 1, Section 3.3.3,     |
| provides the following example of a condition that is not reportable under   |
| these criteria:                                                              |
|                                                                              |
| removal of a system or part of a system from service as part of a planned    |
| evolution for maintenance or                                                 |
| surveillance testing when done in accordance with an approved procedure and  |
| the plant's [technical                                                       |
| specifications] (unless a condition is discovered that could have prevented  |
| the system from performing its                                               |
| function)"                                                                   |
|                                                                              |
| "In this case, RCIC was properly removed from service for planned            |
| maintenance/testing under LCO A2-99-2468 and was not returned to service     |
| until operability was restored.  The intent of the qualifying statement in   |
| NUREG- 1022 (i.e., unless a condition is discovered that could have          |
| prevented the system from performing its function) is to ensure that         |
| pre-existing operability concerns that are discovered during maintenance     |
| activities are reported.  It is not intended to require reporting of         |
| conditions, introduced by the maintenance/testing activity, that are         |
| identified and corrected prior to returning the system to service.  This is  |
| supported by Example 14 for this section of NUREG-1022.  Example 14 deals    |
| with a two-train system in which the wrong lubricant is placed in [one] pump |
| during maintenance activities.  NUREG-1022 states that this condition would  |
| not be reportable if testing would clearly identify the error.  This example |
| is similar to the RCIC inoperability in that testing identified the problem  |
| prior to returning the system to service."                                   |
|                                                                              |
| "Carolina Power & Light Company has determined that this event does not meet |
| the 10 CFR 50.72 or 10 CFR 50.73 reporting criteria, and the notification    |
| for Event Number 36460 is retracted."                                        |
|                                                                              |
| "Supporting information:"                                                    |
|                                                                              |
| "10 CFR 50.72(b)(2) Four-hour reports.  If not reported under paragraphs (a) |
| or (b)(1) of this section, the licensee shall notify the NRC as soon as      |
| practical and in all cases, within four hours of the occurrence of any of    |
| the following:  (iii) any event or condition that alone could have prevented |
| the fulfillment of the safety function of structures or systems that are     |
| needed to:  (A) shut down the reactor and maintain it in a safe shutdown     |
| condition, (B) remove residual heat, (C) control the release of radioactive  |
| material, or (D) mitigate the consequences of an accident."                  |
|                                                                              |
| "10 CFR 50.73(a)(2) The licensee shall report:  (v) Any event or condition   |
| that alone could have prevented the fulfillment of the safety function of    |
| structures or systems that are needed to:  (A) shut down the reactor and     |
| maintain it in a safe shutdown condition, (B) remove residual heat, (C)      |
| control the release of radioactive material, or (D) mitigate the             |
| consequences of an accident."                                                |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R2DO (Boland).                                          |
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+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36513       |
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| REP ORG:  WISCONSIN ELECTRIC POWER COMPANY     |NOTIFICATION DATE: 12/15/1999|
|LICENSEE:  K-RAY                                |NOTIFICATION TIME: 17:54[EST]|
|    CITY:  KENOSHA                  REGION:  3  |EVENT DATE:        12/15/1999|
|  COUNTY:                            STATE:  WI |EVENT TIME:             [CST]|
|LICENSE#:  48-16729-01           AGREEMENT:  N  |LAST UPDATE DATE:  12/15/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SHEAR           R3      |
|                                                |KEIN RAMSEY (FAX)    NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KJELL JOHANSEN               |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CDEG 21.21(c)(3)(i)      DEFECTS/NONCOMPLIANCE  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| K-RAY 706P SOURCE HOLDER DEVELOPED CRACK                                     |
|                                                                              |
| The licensee discovered a crack, about 2-3 inches in length, in the K-Ray    |
| 706P source holder, possibly in a weld.  The gauge, containing a 10-mCi      |
| Cs-137 source, is in a radioactive labeled room under a coal pipe at the     |
| Pleasant Prairie Plant, and it has been wrapped with plastic and labeled     |
| with radioactive stickers.  K-Ray has been notified and will replace the     |
| gauge before the end of the year.  A 30-day written report will follow.      |
|                                                                              |
| (Call the NRC operations officer for a contact telephone number.)            |
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|Research Reactor                                 |Event Number:   36514       |
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| FACILITY: UNIV OF MICHIGAN                     |NOTIFICATION DATE: 12/15/1999|
|   RXTYPE: 2000 KW POOL                         |NOTIFICATION TIME: 21:56[EST]|
| COMMENTS:                                      |EVENT DATE:        12/14/1999|
|                                                |EVENT TIME:             [EST]|
|                                                |LAST UPDATE DATE:  12/15/1999|
|    CITY:  ANN ARBOR                REGION:  3  +-----------------------------+
|  COUNTY:  WASHTENAW                 STATE:  MI |PERSON          ORGANIZATION |
|LICENSE#:  R-28                  AGREEMENT:  N  |GARY SHEAR           R3      |
|  DOCKET:  05000002                             |THEODORE MICHAELS    NRR     |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  CHRISTOPHER BECKER           |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| TECHNICAL SPECIFICATION VIOLATION - 24 HOUR REPORT                           |
|                                                                              |
| "This is the report on a violation of Technical Specification 3.2.1.  Due to |
| the incorrect connection of the high voltage to the compensated voltage      |
| connection of a compensated wide range ion chamber, the Log N Channel        |
| required in Table 3.1, Required Safety Channels, was inoperable during the   |
| reactor startup on 14 December 1999.  Review of the power level indication   |
| from the other nuclear instrumentation channels shows that no limiting       |
| safety system settings were approached during the reactor startup.           |
|                                                                              |
| "Indications from the operable nuclear instruments and temperature system    |
| indicate that no limiting safety system settings were approached.            |
| Determination of the response of the period portion of the Log N system      |
| compared to the periods derived from other properly responding nuclear       |
| instrument channels indicates that the period circuit was measuring periods  |
| of similar magnitude and that the 30-second period for reactor control rod   |
| withdrawal inhibit was not challenged."                                      |
|                                                                              |
| There were three root causes identified:  (1) The Log N circuit and the      |
| linear level circuit are both compensated ion chambers.  However, the bridge |
| connections are opposite, and the operators used the linear connections to   |
| make up the Log N connections.  (2) The operators knew or should have known  |
| that an abnormal reading of the Log N circuit was possible after             |
| maintenance, and (3) the reactor startup procedure specifies that operators  |
| are to "Hold" power at 500 kW to perform the checks, but it has become       |
| acceptable to slowly move through the 500 kW point and record the reading.   |
| Also, the calorimetric procedure specifies that after a 1 MW calorimetric,   |
| the Log N channel should indicate 40-100% (it indicated 25%).                |
|                                                                              |
| The reactor was shut down from full power (2 MW) and will not be restarted   |
| for sustained operation until an operational review of this reportable       |
| occurrence and other non-reportable events is made and presented to the      |
| Safety Review Committee (SRC).  An outside review of recent operations is    |
| being sought and is hoped to be completed prior to requesting permission     |
| from the Director and the SRC for sustained operation.                       |
|                                                                              |
| The following other measures are planned:  Labeling of the cable connections |
| for all the nuclear instrument detectors will be reviewed and improved;      |
| possible design changes to make the connectors have different                |
| configurations.  Operational training will be given on procedures, and       |
| practical performances will be evaluated.                                    |
|                                                                              |
| The licensee notified the NRC Project Manager (Theodore Michaels) and NRC    |
| Inspector (Thomas Dragoun).                                                  |
|                                                                              |
| (Call the NRC operations officer for a contact telephone number.)            |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36515       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 12/16/1999|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 01:01[EST]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        12/15/1999|
+------------------------------------------------+EVENT TIME:        23:25[EST]|
| NRC NOTIFIED BY:  WILSON                       |LAST UPDATE DATE:  12/16/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ANN BOLAND           R2      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING A BUNKER-C OIL SPILL AT THE FOSSIL UNITS      |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Units 1 and 2 (fossil) are notifying [the Department of Environmental       |
| Resource Management (DERM)] of [a] Bunker-C oil spill on [a] permeable       |
| surface.  [It is] estimated that 100 - 150 gallons of bunker C [are]         |
| contained by an earth/rock berm around the fuel tank."                       |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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