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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
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.) |
| |
| *** 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 |
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| 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
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| "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. |
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|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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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021