Event Notification Report for April 26, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/25/2000 - 04/26/2000
** EVENT NUMBERS **
36927 36928 36929 36930
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|Power Reactor |Event Number: 36927 |
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| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/25/2000|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 13:59[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/25/2000|
+------------------------------------------------+EVENT TIME: 11:02[EDT]|
| NRC NOTIFIED BY: M. JAQUIN |LAST UPDATE DATE: 04/25/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|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 |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| REACTOR CORE ISOLATION COOLING (RCIC) STEAM FLOW INSTRUMENTS DECLARED |
| INOPERABLE |
| |
| RCIC steam flow instruments for both Division 1 & 2 became inoperable. |
| Inoperability of these trip units were based upon erratic indications on the |
| trip units. RCIC was subsequently declared inoperable as a result of the |
| required Technical Specification 3.3.2 action for the inoperability of the |
| steam flow instrument which required the isolation of RCIC steam supply |
| line. A 7 day Limiting Condition of Operation for RCIC was entered per |
| Technical Specification 3.7.3 when RCIC steam supply line was isolated. |
| Actions are being taken to correct RCIC steam flow instrument erratic |
| indications. All Emergency Core Cooling Systems and the Emergency Diesel |
| Generators are fully operable if needed. |
| |
| The NRC Resident Inspector was notified of this event by the licensee. |
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|Power Reactor |Event Number: 36928 |
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| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 04/25/2000|
| UNIT: [3] [4] [] STATE: FL |NOTIFICATION TIME: 15:22[EDT]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 04/25/2000|
+------------------------------------------------+EVENT TIME: 15:00[EDT]|
| NRC NOTIFIED BY: C. MOWREY |LAST UPDATE DATE: 04/25/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PAUL FREDRICKSON 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 |
|4 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| OFFSITE NOTIFICATION MADE TO THE STATE OF FLORIDA CONCERNING LOW LEVEL FIXED |
| SURFACE CONTAMINATION FOUND ON SCAFFOLDING EQUIPMENT RECEIVED FROM A |
| VENDOR. |
| |
| While performing a routine survey, Turkey Point Health Physics personnel |
| discovered low levels of radioactivity on several pieces of scaffolding |
| knuckles and elbows received from a vendor. The knuckles never entered the |
| site's radiologically controlled area. These items were counted in a Small |
| Article Monitor (SAM) and indicated low level contamination was present. In |
| total 12 out of approximately 3,000 items surveyed indicated the presence of |
| low level fixed activity. The highest level measured was 15,833 |
| disintegration's per minute (DPM) when counted on the SAM and 125 net (above |
| background) counts per minute using a standard HP-210 probe. Isotopic |
| analysis indicates Cobalt-60 and Cesium-137. No loose surface contamination |
| was found. The items identified with low level fixed contamination are now |
| being held inside the Turkey Point radiologically controlled area. |
| |
| The NRC Resident Inspector was notified of this event notification by the |
| licensee. |
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|Power Reactor |Event Number: 36929 |
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| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 04/25/2000|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 16:21[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 04/25/2000|
+------------------------------------------------+EVENT TIME: 15:45[EDT]|
| NRC NOTIFIED BY: W. FIEDLER |LAST UPDATE DATE: 04/25/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE R1 |
|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 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE. |
| |
| HPCI inverter failure alarm was received at 1545ET. An operator checked the |
| power breakers to the inverter and found them closed. The inverter reset |
| itself at 1551 ET. HPCI was declared inoperable and a 14 day limiting |
| condition of operation was entered per Technical Specification 3.5. |
| Licensee investigating HPCI inverter problem. All other Emergency Core |
| Cooling Systems and the Emergency Diesel Generators are fully operable. |
| |
| |
| The NRC Resident Inspector was notified of the event by the licensee. |
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|Power Reactor |Event Number: 36930 |
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| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 04/26/2000|
| UNIT: [] [] [3] STATE: AL |NOTIFICATION TIME: 03:23[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 04/25/2000|
+------------------------------------------------+EVENT TIME: 23:42[CDT]|
| NRC NOTIFIED BY: RODNEY NACOSTE |LAST UPDATE DATE: 04/26/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PAUL FREDRICKSON R2 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
| | |
|3 N N 0 Cold Shutdown |0 Cold Shutdown |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| VARIOUS ESF ACTUATIONS DUE TO RPS BUS 3B DE-ENERGIZING AS A RESULT OF A |
| FAILED RELAY |
| |
| "At 23:42 [CDT] the RPS bus 3B de-energized causing PCIS Group 2 and Group 6 |
| isolation valves to automatically close. A burnt relay was the initiating |
| condition. Group 2 outboard drywell equipment drain valve and drywell floor |
| drain valve closed. Group 6 drywell radiation monitor isolation valves |
| closed. All other expected group isolations occurred along with the |
| automatic starts of SBGTS and CREVS. |
| |
| "Unit 3 is in Mode 5 with primary containment integrity not required. |
| |
| "This event is reportable under criteria 50.72.b.2.ii : Any event or |
| condition that results in manual or automatic actuation of any engineered |
| safety feature (ESF), including the reactor protection system (RPS)." |
| |
| RPS bus 3B was re-energized from its alternate power supply. Electricians |
| are currently troubleshooting the cause of the failed relay. There was no |
| electrical maintenance or testing ongoing at the time of the relay failure. |
| |
| The licensee informed the NRC Resident Inspector. |
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Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021