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Event Notification Report for September 21, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           09/20/1999 - 09/21/1999

                              ** EVENT NUMBERS **

36091  36197  36201  36202  36203  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   36091       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 08/31/1999|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 02:21[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        08/30/1999|
+------------------------------------------------+EVENT TIME:        22:22[CDT]|
| NRC NOTIFIED BY:  GREEN                        |LAST UPDATE DATE:  09/21/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHARLES CAIN         R4      |
|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                                   
+------------------------------------------------------------------------------+
| FAILURE OF A SINGLE TRAIN SYSTEM THAT IS REQUIRED TO MITIGATE THE            |
| CONSEQUENCES OF AN ACCIDENT                                                  |
|                                                                              |
| On 8/30/99 at 2222 while performing maintenance on SW-MOV-650MV, Reactor     |
| Equipment Cooling (REC) heat exchanger "A" Service Water (SW) Outlet Valve,  |
| SW-MOV-650MV was manually opened while disconnecting Limit Switches. The     |
| valve was opened to a point that allowed 2475 Gallons Per Minute (GPM) of    |
| service water flow thru the "A" REC heat exchanger.  Service water flow      |
| greater than 1200 GPM thru the "A" REC heat exchanger results in the "A"     |
| Service Water subsystem being inoperable (LCO 3.7.2) which requires          |
| restoration of the "A" Service Water subsystem within 30 days.  LCO 3.8.1    |
| was entered for Diesel Generator 1 (DG1) because it was declared inoperable  |
| due to the Service Water being inoperable. The Control Room Emergency        |
| Filtration System (CREFS), which is a single train system, was aligned to a  |
| bus that would be powered from DG1 in the event of an accident.  This        |
| condition resulted in CREFS also being declared inoperable (LCO 3.7.4)       |
|                                                                              |
| When the increased flow though the "A" REC heat exchanger was discovered by  |
| a Control Room Operator, the Valve Technicians performing the maintenance    |
| were instructed to manually close SW-MOV-650MV until Service Water flow      |
| through the "A" REC Heat Exchanger was reduced below 1200 GPM, which was     |
| completed at 2238. All of the previously mentioned LCO's were also exited at |
| this time.                                                                   |
|                                                                              |
| At the time this event occurred both sources of offsite power were available |
| and DG2 was determined to not be affected by this condition.                 |
|                                                                              |
| The Resident Inspector was notified.                                         |
|                                                                              |
|                                                                              |
| *** UPDATE ON 9/21/99 @ 0259 BY GREEN TO GOULD ***    EVENT RETRACTION       |
|                                                                              |
| SUBSEQUENT INVESTIGATION HAS DETERMINED THAT D/G#1 WAS ALWAYS CAPABLE OF     |
| PERFORMING ITS SAFETY FUNCTION DURING THE EVENT.  THEREFORE, CREFS REMAINED  |
| OPERABLE AND THIS EVENT IS BEING RETRACTED.                                  |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36197       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 09/18/1999|
|    UNIT:  [1] [] []                 STATE:  WI |NOTIFICATION TIME: 13:29[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        09/18/1999|
+------------------------------------------------+EVENT TIME:        01:00[CDT]|
| NRC NOTIFIED BY:  JOHN SELL                    |LAST UPDATE DATE:  09/20/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GARY SHEAR           R3      |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|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                                   
+------------------------------------------------------------------------------+
| RESPONSE TO NRC BULLETIN 80-24 REGARDING LEAKAGE OF SERVICE WATER INTO       |
| REACTOR CONTAINMENTS (24-HOUR REPORT)                                        |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 0100 [CDT] on 09/18/99, a pin hole leak was identified on the 'A' Unit 1 |
| containment fan cooler.  The unit had been in a 72-hour [limiting condition  |
| for operation (LCO)] for partial blockage of this cooler by zebra mussels.   |
| The leak was discovered during treatment for the zebra mussels.  The LCO     |
| expires at 1035 [CDT] on 09/19/99.  The plan is presently to isolate the     |
| leaking tube section and restore the cooler as operable but degraded."       |
|                                                                              |
| There was nothing unusual or not understood and all systems functioned as    |
| required.  The licensee stated that there are four containment fan coolers   |
| per unit.  The licensee also stated the NRC Bulletin 80-24 has been          |
| superceded but that they are still committed to the provisions of this       |
| bulletin.                                                                    |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE AT 1345 ON 09/20/99 FROM JOHN SELL TAKEN BY JOLLIFFE * * *      |
|                                                                              |
| Upon further review of this event, the licensee determined that only leakage |
| greater than 1 GPM should be reportable to the NRC and that reporting this   |
| event to the NRC was a conservative action.  The 1 GPM value is consistent   |
| with Point Beach Tech Spec requirements for evaluation of RCS leakage.  The  |
| pinhole leak did not meet this criteria.  Thus, the licensee desires to      |
| retract this event.  The 72 hour LCO for the 'A' Unit 1 containment fan      |
| cooler was exited at 2140 CDT on 09/18/99.  The fan cooler remains operable  |
| but degraded.                                                                |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  The NRC Operations        |
| Officer notified the R3DO Roger Lanksbury.                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36201       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 09/20/1999|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 03:59[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        09/20/1999|
+------------------------------------------------+EVENT TIME:        00:09[EDT]|
| NRC NOTIFIED BY:  CHISM                        |LAST UPDATE DATE:  09/20/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |CHRIS CHRISTENSEN    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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       4        Startup          |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE REACTOR WAS MANUALLY SCRAMMED AT 4% POWER.                               |
|                                                                              |
| While in mode 2 at approximately 450 psig during unit 2 startup, an          |
| automatic group 1 (MSIV's, steam line drain and reactor sample valves)       |
| isolation occurred. The main steam line isolation caused reactor pressure to |
| rise. The licensee inserted control rods and stabilized reactor pressure at  |
| approximately 950 psig. After verifying that the automatic isolation signal  |
| had cleared, the licensee equalized around and reopened the MSIV's in order  |
| to restart a reactor feed pump and restore RPV level control. When feed flow |
| was restored, a rapid power rise was observed prompting the licensee to      |
| insert a manual reactor scram.  All control rods fully inserted as expected, |
| and no ECCS actuation occurred or safety relief valves lifted.  The licensee |
| took conservative action to insert a manual scram.                           |
|                                                                              |
| The systems affected by the automatic isolations were returned to service.   |
| Unit 2 is currently in hot shutdown. The licensee has formed an event        |
| investigation team for this event.  The cause of the automatic isolation has |
| not been positively determined, but it appears the isolation occurred when   |
| the licensee was draining the condenser pressure sensing lines for the       |
| pressure transmitters resulting in a Group 1 isolation on low condenser      |
| vacuum in accordance with 0GP-02, APPROACH TO CRITICALITY AND PRESSURIZATION |
| OF THE REACTOR.                                                              |
|                                                                              |
| The Resident Inspector was notified.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36202       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 09/20/1999|
|    UNIT:  [] [3] []                 STATE:  PA |NOTIFICATION TIME: 17:53[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        09/20/1999|
+------------------------------------------------+EVENT TIME:        14:35[EDT]|
| NRC NOTIFIED BY:  CAMERON CAMPBELL             |LAST UPDATE DATE:  09/20/1999|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT SUMMERS       R1      |
|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          Y       82       Power Operation  |82       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - Channel 'B' manual half scram signal received due to an electrical short   |
| in the reactor protection system logic -                                     |
|                                                                              |
| A channel 'B' manual half scram signal was received during modification      |
| installation when drilling activities inadvertently contacted a wire in the  |
| reactor protection system (RPS) logic.  The shorted wire resulted in a blown |
| fuse which deenergized power to the channel 'B' manual half scram logic.     |
| The outboard scram discharge volume vent valves and drain valve shut per     |
| design on receipt of the channel 'B' manual half scram signal.               |
|                                                                              |
| The damaged RPS wire has been repaired and the fuse has been replaced.  The  |
| channel 'B' manual half scram signal has been reset and the outboard scram   |
| discharge volume vent valves and drain valve have been reopened per station  |
| procedures by 1638.  The channel 'B' manual half scram signal and subsequent |
| reset had no impact on plant operation.                                      |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36203       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: THREE MILE ISLAND        REGION:  1  |NOTIFICATION DATE: 09/21/1999|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 00:56[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP            |EVENT DATE:        09/21/1999|
+------------------------------------------------+EVENT TIME:        00:50[EDT]|
| NRC NOTIFIED BY:  BOYER                        |LAST UPDATE DATE:  09/21/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |ROBERT SUMMERS       R1      |
|10 CFR SECTION:                                 |                             |
|AMED 50.72(b)(2)(v)      OFFSITE MEDICAL        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIALLY CONTAMINATED INJURED PERSON TRANSPORTED OFFSITE.                 |
|                                                                              |
| THE LICENSEE TRANSPORTED AN INDIVIDUAL WHO INJURED HIS LOWER BACK WHILE      |
| WORKING INSIDE CONTAINMENT ON THE UPPER MANWAY TO THE HERSHEY MEDICAL        |
| CENTER.  HE MAY HAVE BEEN CONTAMINATED, SO HE WAS ACCOMPANIED BY HEALTH      |
| PHYSICS PERSONNEL TO THE HOSPITAL.                                           |
|                                                                              |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED                                      |
|                                                                              |
| *** UPDATE ON 9/21/99 @ 0209 BY BOYER TO GOULD ***                           |
|                                                                              |
| THE INDIVIDUAL WAS NOT CONTAMINATED, HOWEVER, HIS CLOTHING WAS AND IT IS     |
| BEING RETURNED TO THE SITE.                                                  |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
+------------------------------------------------------------------------------+