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Event Notification Report for January 4, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/03/2000 - 01/04/2000

                              ** EVENT NUMBERS **

36494  36513  36556  36557  36558  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   36494       |
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| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 12/07/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 20:21[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        12/07/1999|
+------------------------------------------------+EVENT TIME:        17:55[CST]|
| NRC NOTIFIED BY:  JIM McKAY                    |LAST UPDATE DATE:  01/03/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |PATRICK HILAND       R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       92       Power Operation  |92       Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| INOPERABILITY OF HPCI DUE TO A LOOSE PIPE SUPPORT                            |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "During normal plant operation the High Pressure Core Injection (HPCI)       |
| system was declared inoperable [in accordance with] Technical Specification  |
| section 3.5.A.3.g.  HPCI is inoperable due to an inoperable pipe support on  |
| the steam supply to the HPCI drive turbine.  The support was observed to be  |
| loose, and the anchor bolts on the base of the support are pulled out of the |
| wall approximately 3/8".  HPCI is in a 14-day [limiting condition for        |
| operation]."                                                                 |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| *** RETRACTION ON  01/03/00 AT 1723ET FROM T. ROGERS TAKEN BY MACKINNON ***  |
|                                                                              |
| The support was repaired, and the system was returned to its normal standby  |
| condition. Subsequent analysis showed that the HPCI system remained operable |
| with the support in the degraded condition.  Therefore, the licensee is      |
| retracting this event notification.  The licensee notified State, Local ,    |
| and the NRC Resident Inspector of this retraction.                           |
|                                                                              |
| The NRC R3DO (MADERA) was notified of this retraction.                       |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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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:  01/03/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |GARY SHEAR           R3      |
|                                                |KEVIN RAMSEY (FAX)           |
+------------------------------------------------+                             |
| 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                                   
+------------------------------------------------------------------------------+
| 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.)            |
|                                                                              |
| *** RETRACTION ON 01/03/00 AT 1707ET FROM KJELL JOHANSEN TAKEN BY MACKINNON  |
| ***                                                                          |
|                                                                              |
| The licensee is retracting this report because the crack in the K-RAY 706P   |
| does not meet the definition of  Substantial Safety Hazard found in 10 CFR   |
| 21.3. Per  10 CFR 21.3 Substantial Safety Hazard "means a loss of safety     |
| function to the extent that there is a major reduction in the degree of      |
| protection provided to public health and safety for any facility or activity |
| licensed, other than for export, etc."  The contact radiation level on the   |
| cracked K-RAY 706P was the same level as the K-RAY 706P without a crack,     |
| 1.5mrem/hr.  A 30 day report will be filed.   R3DO (MADERA) notified.        |
| Facsimile sent to Kevin Ramsey (NMSS)                                        |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36556       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 01/03/2000|
|    UNIT:  [] [2] []                 STATE:  WI |NOTIFICATION TIME: 12:33[EST]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        01/03/2000|
+------------------------------------------------+EVENT TIME:        11:20[CST]|
| NRC NOTIFIED BY:  JOHN SELL                    |LAST UPDATE DATE:  01/03/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| "C" CHARGING PUMP APPENDIX  "R" CONCERN                                      |
|                                                                              |
| During the Appendix "R" rebaselining project it was discovered that the Unit |
| 2 "C" charging pump (Positive Displacement Pump) may require replacement of  |
| a control power fuse for the equipment to be available following certain     |
| postulated fires.  10CFR 50 Appendix "R" does not allow repair of hot        |
| shutdown equipment.  The replacement of fuses is considered a repair.  The   |
| "C" charging pump is relied on for Unit 2 charging following certain         |
| postulated fires.  This situation could potentially leave Unit 2 without any |
| charging pumps following certain postulated fires which would be outside the |
| plants Appendix "R" design basis.  Fire rounds will be instituted in         |
| affected fire zones until this issue is resolved.                            |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36557       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OCONEE                   REGION:  2  |NOTIFICATION DATE: 01/03/2000|
|    UNIT:  [] [] [3]                 STATE:  SC |NOTIFICATION TIME: 14:13[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE:        01/03/2000|
+------------------------------------------------+EVENT TIME:        12:57[EST]|
| NRC NOTIFIED BY:  MICHAEL DUNTON               |LAST UPDATE DATE:  01/03/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHRIS CHRISTENSEN    R2      |
|10 CFR SECTION:                                 |                             |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|                                                   |                          |
|3     A/R        Y       55       Power Operation  |0        Hot Standby      |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL TURBINE TRIP FROM 28% CAUSED AN  AUTOMATIC REACTOR TRIP               |
|                                                                              |
| Unit 3 was initially at 100% power level when a Stator Coolant Runback       |
| initiated due to High Stator Coolant Temperature.  Turbine Runback to 0 MWe  |
| with Reactor power at approximately 28% power.  The Turbine was manually     |
| tripped and the Reactor automatically tripped on Turbine to Reactor          |
| anticipatory Trip.  All rods fully inserted into the core. A couple of Once  |
| Through Steam Generator Safety Relief Valves opened/closed.   Main Feedwater |
| Water remained inservice and steam is being dumped to the condenser to       |
| maintain a Tave no load condition.  All Emergency  Core Cooling systems,     |
| Diesel generator, and their Keowee system are fully operable if needed.      |
|                                                                              |
| The licensee believes that the Stator Water Cooling Temperature Control      |
| Valve (TCV) failed closed which caused the Stator water to bypass its        |
| coolers. The licensee also stated that it took approximately 3 to 4 minutes  |
| to reduce reactor power from 100% to 28% at which point the Turbine was      |
| manually tripped. The operators believed they were below the Turbine         |
| trip/Reactor Trip setpoint when the Main Turbine was manually tripped.  One  |
| of the three Turbine Trip/Reactor Trip setpoint bypasses was bypassed but    |
| the other two were right on their bypass setpoint when the Turbine was       |
| manually tripped.                                                            |
|                                                                              |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
|                                                                              |
| *** UPDATE ON 01/03/00 AT 1640 HOURS FROM DUNTON TAKEN BY MACKINNON ***      |
|                                                                              |
| The licensee revised the above event report to state that the Turbine was    |
| manually tripped at 55% reactor power by orders of the SRO because of        |
| potential electrical damage to the generator.  Therefore the licensee was    |
| expecting the reactor to automatically trip when the Turbine was manually    |
| tripped.  R2DO (Chris Christensen) notified.                                 |
|                                                                              |
| NRC Resident Inspector was notified of this update by the licensee.          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36558       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 01/03/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 16:14[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/03/2000|
+------------------------------------------------+EVENT TIME:        14:45[EST]|
| NRC NOTIFIED BY:  M ABRAMSKI                   |LAST UPDATE DATE:  01/03/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JIMI YEROKUN         R1      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE.                  |
|                                                                              |
| During Technical Specification required surveillance testing an oil leak was |
| detected on a fitting in the HPCI hydraulic governor control system (EGR     |
| actuator).  It was determined that had this leak developed during accident   |
| conditions, the HPCI system may not have been able to perform it's intended  |
| function for the duration of time required.  The licensee entered the        |
| appropriate Technical Specification for declaring HPCI inoperable (7 day     |
| Limiting Condition of Operation).  All other Emergency Core Cooling Systems  |
| and the Reactor Core Isolation Cooling system are fully operable if needed.  |
| The licensee is preparing to repair the HPCI hydraulic governor control      |
| system oil leak.                                                             |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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