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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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35899       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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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