Event Notification Report for July 7, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/06/1999 - 07/07/1999
** EVENT NUMBERS **
35897 35898 35899
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|Power Reactor |Event Number: 35897 |
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| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 07/06/1999|
| UNIT: [] [2] [] STATE: VA |NOTIFICATION TIME: 02:44[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/06/1999|
+------------------------------------------------+EVENT TIME: 02:04[EDT]|
| NRC NOTIFIED BY: LISA HILBERT-SEMMES |LAST UPDATE DATE: 07/06/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PAUL FREDRICKSON R2 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Hot Shutdown |0 Intermediate Shut|
| | |
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EVENT TEXT
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| MODE CHANGE INITIATED AS PART OF A TECHNICAL SPECIFICATION REQUIRED |
| SHUTDOWN |
| |
| "At 1810 hours on 7-5-99, with Surry Power Station Unit 2 at Hot Shutdown |
| (HSD) following a reactor trip, the 'A' Cold Leg Loop Stop Valve (Mark |
| number 2-RC-MOV-2591) was removed from it's backseat in accordance with |
| station procedure 2-GOP-2.4. Upon reopening the valve, full open indication |
| was not received. In accordance with Technical Specification 3.17.1 and |
| 3.0.1, a 30 hour clock to Cold Shutdown (CSD) LCO was started. The valve was |
| de-energized by opening it's breaker. A cooldown to CSD was initiated at |
| 2050 on 7-5-99. At 0204 on 7-6-99, a review of Station procedures and |
| 10CFR50.72 determined that a one hour report was required for commencing the |
| RCS cooldown in accordance with the Technical Specification LCO. |
| |
| "There were no radiation releases due to this event, nor were there any |
| personnel injuries or contamination events. |
| |
| "Unit 2 is currently at Intermediate Shutdown with RCS cooldown in progress |
| in accordance with station procedures. |
| |
| "Unit 1 was not affected by this event and remains stable at 100% power and |
| 824 MWe. |
| |
| "This event is being reported in accordance with 10CFR50.72(b)(1)(i)(A)." |
| |
| The Licensee informed the NRC Resident Inspector. |
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|Power Reactor |Event Number: 35898 |
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| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 07/06/1999|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 14:37[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/06/1999|
+------------------------------------------------+EVENT TIME: 13:30[EDT]|
| NRC NOTIFIED BY: DON ROLAND |LAST UPDATE DATE: 07/06/1999|
| HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DEGRADED/UNANALYZED CONDITION |
| |
| During a Unit 1 forced outage, the licensee determined that the 'C' outboard |
| Main Steam Isolation Valve (MSIV) was unable to fully close. Based on the |
| as-found valve configuration, it is believed that the MSIV volume would not |
| reach required test pressure, therefore actual leak rate testing was not |
| performed. This report documents exceeding overall MSIV maximum pathway |
| acceptance criteria of 300 scfh. |
| |
| The licensee determined that the valve disc had separated from the stem. |
| |
| See Event 35884 for further information. |
| |
| The licensee has notified the NRC resident inspector. |
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|Power Reactor |Event Number: 35899 |
+------------------------------------------------------------------------------+
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| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 07/07/1999|
| UNIT: [1] [] [] STATE: SC |NOTIFICATION TIME: 02:41[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 07/07/1999|
+------------------------------------------------+EVENT TIME: 01:10[EDT]|
| NRC NOTIFIED BY: MICHAEL DUNTON |LAST UPDATE DATE: 07/07/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MARK LESSER R2 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A/R Y 15 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR TRIP DUE TO LOSS OF MAIN FEEDWATER |
| |
| The unit automatically tripped due to the loss of all main feedwater flow |
| after the main feedwater pump tripped on low suction pressure. All control |
| rods inserted following the trip. Emergency feedwater actuated as |
| expected. |
| |
| The licensee reported that two main steam relief valves remained open |
| following the trip, but reclosed after steam generator pressure was reduced |
| to 920 psig. The unit is currently stable in Hot Standby, with steam |
| generator levels being maintained by the motor driven emergency feedwater |
| pumps, and decay heat being relieved to the main condenser via the turbine |
| bypass valves. |
| |
| The NRC resident inspector has been informed 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