Home
> NRC Library
> Document Collections
> Reports Associated With Events
> Event Notification Reports > 1999
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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35507 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35547 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35548 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35549 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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 |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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
+------------------------------------------------------------------------------+
| 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). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35551 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+