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Event Notification Report for April 7, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           04/06/1999 - 04/07/1999

                              ** EVENT NUMBERS **

35507  35547  35548  35549  35550  35551  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Fuel Cycle Facility                              |Event Number:   35507       |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 03/25/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 01:36[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/24/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        19:00[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  04/06/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |PATRICK HILAND       R3      |
|  DOCKET:  0707002                              |ROBERT PIERSON       NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|OCBC 76.120(c)(2)(iii)   REDUNDANT EQUIP INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| TSR allowed one of two smoke detectors to be inoperable during withdrawal    |
| operations when both smoke detectors have to be operable during withdrawal   |
| operations.                                                                  |
|                                                                              |
| On March 10, 1999, Operations personnel identified a deficiency in a TSR     |
| requirement for the Pigtail line Isolation System at ERP (extended range     |
| product), LAW (low assay withdrawal), and TAILS, (TSR 2.5.3.4). The TSR      |
| required action allowed continued withdrawal operations if one (1) smoke     |
| detector was inoperable.  The Pigtail Line Isolation System requires two (2) |
| Pyrotronics Smoke Detectors to actuate for the isolation valve to close.     |
| Operation personnel initiated a Compensatory Action (CA-99-009) for this     |
| anomaly to isolate the withdrawal cylinder and manifold per TSR 2.5.3.4b if  |
| one smoke detector is declared inoperable.                                   |
|                                                                              |
| Initially there was no evidence that the Pigtail Line Isolation System had   |
| been allowed to operate any applicable mode (modes II or III) with one or    |
| more inoperable smoke head.  As a follow up investigation to this            |
| deficiency, a search of the BPS system (problem report database) was         |
| conducted.  This search identified that on July 8, 1998, a Pyrotronic smoke  |
| head at the Law IA withdrawal position had been declared inoperable and      |
| cylinder filling operations had been allowed to continue.                    |
|                                                                              |
| This event is reportable due to a Safety System required by the TSR not      |
| being available or operable and no redundant equipment was available to      |
| perform the required safety function.                                        |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the certificate     |
| holder.                                                                      |
|                                                                              |
| * * * UPDATE at 1645EDT on 4/6/99 from Keith Williamson to S.Sandin * * *    |
|                                                                              |
| "On April 6, 1999 at 0850, the Plant Shift Superintendent retracted the      |
| above event.  Based on completion of Engineering Evaluation                  |
| EVAL-OS-1999_0202 Rev. 0, the plant has determined that the system would     |
| have performed its designed safety function in this particular instance."    |
|                                                                              |
| The certificatee informed the NRC Resident Inspector and the DOE Site        |
| Representative.  Notified R3DO(Burgess) and NMSS EO(Camper).                 |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35547       |
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| FACILITY: RIVER BEND               REGION:  4  |NOTIFICATION DATE: 04/06/1999|
|    UNIT:  [1] [] []                 STATE:  LA |NOTIFICATION TIME: 06:01[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        04/06/1999|
+------------------------------------------------+EVENT TIME:        01:50[CDT]|
| NRC NOTIFIED BY:  RUSS GODWIN                  |LAST UPDATE DATE:  04/06/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TOM STETKA           R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADVERTENT INITIATION OF DIVISION 1 STANDBY SERVICE WATER DURING            |
| PERFORMANCE OF COLD SHUTDOWN VALVE STROKE TESTING                            |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "At 0150 [CDT], on April 6, 1999, with the plant in Mode 5 (Refueling),      |
| Division One Standby Service Water initiated due to Reactor Component        |
| Cooling Water low pressure."                                                 |
|                                                                              |
| "The low-pressure condition was inadvertently created during the performance |
| of cold shutdown valve stroke testing."                                      |
|                                                                              |
| "The Division One Standby Service Water System is not required to be         |
| OPERABLE in the current plant MODE; however, the system was in standby and   |
| responded as expected.  Operators returned the system to a standby line      |
| up."                                                                         |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35548       |
+------------------------------------------------------------------------------+
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| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 04/06/1999|
|    UNIT:  [1] [2] []                STATE:  MI |NOTIFICATION TIME: 08:00[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/06/1999|
+------------------------------------------------+EVENT TIME:        07:00[EDT]|
| NRC NOTIFIED BY:  DON KOSLOFF                  |LAST UPDATE DATE:  04/06/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE BURGESS        R3      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF THE POTENTIAL COMPROMISE OF SAFEGUARDS INFORMATION.             |
|                                                                              |
| At 0700 EDT on 04/06/99, a potential compromise of safeguards information    |
| was discovered.  Immediate compensatory actions were taken upon discovery.   |
| (Contact the NRC operations officer for additional details and for licensee  |
| contact information.)                                                        |
|                                                                              |
| This issue was reported as a 1-hour event notification in accordance with 10 |
| CFR 73.71(b)(1), Appendix G.                                                 |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35549       |
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| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 04/06/1999|
|    UNIT:  [] [3] []                 STATE:  PA |NOTIFICATION TIME: 10:27[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        04/06/1999|
+------------------------------------------------+EVENT TIME:        09:50[EDT]|
| NRC NOTIFIED BY:  JIM KOVALCHICK               |LAST UPDATE DATE:  04/06/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |FRANK COSTELLO       R1      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| DISCOVERY OF A VULNERABILITY THAT COULD HAVE ALLOWED UNDETECTED ACCESS TO A  |
| VITAL AREA                                                                   |
|                                                                              |
| The licensee discovered a safeguards system degradation related to a vital   |
| area door.  Compensatory actions were taken upon discovery.  (Contact the    |
| NRC operations officer for additional details.)                              |
|                                                                              |
| This issue was reported as a 1-hour report event notification in accordance  |
| with 10 CFR 73.71(b)(1).                                                     |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35550       |
+------------------------------------------------------------------------------+
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| FACILITY: SAINT LUCIE              REGION:  2  |NOTIFICATION DATE: 04/06/1999|
|    UNIT:  [] [2] []                 STATE:  FL |NOTIFICATION TIME: 11:46[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        04/06/1999|
+------------------------------------------------+EVENT TIME:        11:00[EDT]|
| NRC NOTIFIED BY:  ALAN HALL                    |LAST UPDATE DATE:  04/06/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WALTER RODGERS       R2      |
|10 CFR SECTION:                                 |                             |
|ASHU 50.72(b)(1)(i)(A)   PLANT S/D REQD BY TS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |97       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
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| VERY SMALL THROUGH WALL LEAKS ON ECCS SUCTION LINES REQUIRE PLANT SHUTDOWN   |
|                                                                              |
| While the mechanical people were making a normal plant walkdown, they        |
| discovered very small through wall leaks on both emergency core cooling      |
| system (ECCS) suction lines.  The leaks are downstream of the motor operated |
| isolation valves just after the splitter for the connection to the refueling |
| water tank.  Both leaks were discovered due to boric acid buildup on the     |
| '2A' and '2B' ECCS suction lines.  The plant has entered Technical           |
| Specifications 3.5.2, 3.5.3, and 3.0.3 which requires plant shutdown to cold |
| shutdown.  The plant is in the process of shutting down and expects to be    |
| shutdown until the problems are corrected.                                   |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * UPDATE at 1729EDT on 4/6/99 from Alan Hall to S. Sandin * * *          |
|                                                                              |
| "Following discussion with NRR and Region II if the as-found condition of    |
| the low pressure piping, FPL has performed an OPERABILITY evaluation of the  |
| flawed piping in accordance with Generic Letters 91-18 and 90-05 and         |
| concluded that the ECCS piping is OPERABLE.  FPL exited the LCOs and secured |
| the downpower of unit 2 as of 1640 on 4/6/99 following Facility Review Group |
| and management review of the OPERABILITY evaluation.  As discussed with the  |
| NRC, FPL will submit a relief request in a timely manner."                   |
|                                                                              |
| Unit 2 is currently at 28% power.  The licensee intends to increase and hold |
| power at 50%  for grid stabilization.  The licensee informed the NRC         |
| Resident Inspector.  Notified R2DO(Rodgers).                                 |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35551       |
+------------------------------------------------------------------------------+
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| FACILITY: SOUTH TEXAS              REGION:  4  |NOTIFICATION DATE: 04/06/1999|
|    UNIT:  [] [2] []                 STATE:  TX |NOTIFICATION TIME: 14:32[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        04/06/1999|
+------------------------------------------------+EVENT TIME:        11:00[CDT]|
| NRC NOTIFIED BY:  BOB PELL                     |LAST UPDATE DATE:  04/06/1999|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID GRAVES                 |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| UNIT 2 CONTAINMENT AIRLOCK DETERMINED INOPERABLE DURING LAST REFUELING       |
| OUTAGE                                                                       |
|                                                                              |
| "On 10/7/98 during the 2RE06 Refueling outage in Unit 2, The Temporary       |
| Modification used to return power to the Reactor Containment Building (RCB)  |
| personnel airlock did not adequately cover all components necessary to       |
| enable the Instrument Air (IA) Supply Solenoids to be OPENED (IA is a        |
| required support system used to pressurize the airlock door seals).          |
| Therefore, instrument air could not be supplied to the airlock seals within  |
| 30 minutes as required by Technical Specification (TS) 3.9.4.b.  TS 3.9.4    |
| required one airlock door capable of being closed within 30 minutes.  During |
| this time period, when the airlock door was inoperable core alterations were |
| performed. This ACTION was in violation of TS 3.9.4.b.                       |
|                                                                              |
| "This condition is being reported under Section 2G of the Operating License  |
| (NPF-80)."                                                                   |
|                                                                              |
| This condition was discovered while implementing the same Temporary          |
| Modification on Unit 1.  The licensee is conducting a root cause             |
| investigation following which appropriate corrective actions will be         |
| identified.                                                                  |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
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