Event Notification Report for August 12, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/11/1999 - 08/12/1999
** EVENT NUMBERS **
35943 36010 36014 36015 36016 36017 36018 36019 36020 36021 36022
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35943 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/21/1999|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 18:48[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/21/1999|
+------------------------------------------------+EVENT TIME: 18:00[EDT]|
| NRC NOTIFIED BY: MIKE VASELY |LAST UPDATE DATE: 08/11/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JAMES NOGGLE R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 99 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS - SILICONE SEALANT NOT PROPERLY APPLIED TO SOME |
| EQUIPMENT |
| |
| During an engineering inspection of the condition of the sealant used to |
| satisfy environmental qualification requirements, several components were |
| found to have seal conditions that did not meet the Con Edison design |
| specifications. In each case it is believed that the degraded condition |
| identified will not prevent the associated equipment from performing its |
| intended safety functions and operability determinations are being completed |
| to document these conclusions. The specific problems identified are as |
| follows: |
| |
| - MSIV limit switches |
| - Auxiliary feedwater flow indication |
| - Motor driven auxiliary feedwater pumps recirculation valves |
| - City water backup solenoid valves and limit switches to motor driven |
| auxiliary feedwater pumps. |
| |
| An inspection plan is being developed to determine the extent of this |
| condition. |
| |
| The licensee informed the NRC Resident Inspector. |
| |
| *** UPDATE ON 8/11/99 @ 1110 BY BALLETTA TO GOULD *** RETRACTION |
| |
| THE LICENSEE IS RETRACTING THIS EVENT SINCE FURTHER INVESTIGATION |
| DETERMINED, THAT IN ALL CASES WHERE THE COMPONENTS' SEALANT WAS NOT WITHIN |
| THE ACCEPTANCE CRITERIA FOR THE LICENSEE'S DESIGN SPECIFICATION, THE |
| COMPONENTS WERE OPERABLE AND CAPABLE OF PERFORMING THEIR RESPECTIVE SAFETY |
| FUNCTIONS. |
| |
| THE RESIDENT INSPECTOR WILL BE INFORMED. |
| |
| THE REG 1 RDO(GRAY) WAS NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36010 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/10/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 09:49[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/09/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:30[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/12/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS R3 |
| DOCKET: 0707002 |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RICK LARSON | |
| HQ OPS OFFICER: WILLIAM POERTNER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BULLETIN 91-01 24 HOUR REPORT |
| |
| Operations personnel during a walkdown of the seal exhaust system discovered |
| that a nuclear criticality safety analysis (NCSA) requirement, maximum oil |
| volume, could not be verified when an oil level was observed in the pumps |
| separator's sight glass. The pumps in question were used for the highly |
| enriched uranium (HEU) program, and after it's suspension, prior to March |
| 1997, the pumps were placed out of service. Visible oil level in the sight |
| glass without supporting documentation for oil capacity of these pumps |
| constitutes a loss of one control (Volume) for double contingency. The |
| second control (Interaction) was maintained. |
| |
| There was no loss of hazardous/radioactive material or |
| radioactive/radiological contamination exposure as a result of this event. |
| |
| The licensee notified the NRC resident inspector and DOE. |
| |
| *** UPDATE ON 8/12/99 @ 0130 BY SPAETH TO GOULD *** |
| |
| WALKDOWNS OF SEAL EXHAUST PUMPS IN THE X-326 BUILDING REVEALED THAT SEVERAL |
| OLD STYLE/OUT OF SERVICE PUMPS (KDH-80, DVD-8810) HAD INDICATION OF OIL IN |
| THE SEPARATOR SITE GLASS, ABOVE THE LEVEL OF THE OVERFLOW. THIS IS A LOSS |
| OF ONE CONTROL (VOLUME) OF THE DOUBLE CONTINGENCY PRINCIPLE. THE SECOND |
| CONTROL (INTERACTION) REMAINS IN PLACE. THIS UPDATE IS BEING SUBMITTED TO |
| IDENTIFY THE FACT THAT ADDITIONAL PUMPS WERE IDENTIFIED IN WHICH THE MAXIMUM |
| AMOUNT OF OIL COULD NOT BE VERIFIED. |
| |
| THE NRC RESIDENT INSPECTOR AND DOE WERE NOTIFIED BY THE LICENSEE. |
| |
| REG 3 RDO(BURGESS) AND NMSS EO(HICKEY) WERE NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36014 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 08/11/1999|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 10:40[EDT]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 08/11/1999|
+------------------------------------------------+EVENT TIME: 06:40[EDT]|
| NRC NOTIFIED BY: PALMER |LAST UPDATE DATE: 08/11/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES OGLE R2 |
|10 CFR SECTION: | |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | |
|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
+------------------------------------------------------------------------------+
| THE LICENSEE ENTERED AN LCO ACTION STATEMENT DUE TO INCORRECT RADIATION |
| MONITOR SETPOINTS. |
| |
| FOUR CONTAINMENT VENTILATION ISOLATION RADIATION AREA MONITORS WERE |
| DETERMINED TO HAVE A NON-CONSERVATIVE HIGH VALUE FOR BACKGROUND RADIATION |
| LEVEL. THIS RESULTS IN A NON-CONSERVATIVE SETPOINT FOR THE CONTAINMENT |
| VENTILATION ISOLATION FUNCTION. THIS CONDITION ALSO PLACED THE PLANT IN AN |
| LCO ACTION STATEMENT REQUIRING THEM TO ISOLATE NORMAL CONTAINMENT PURGE, |
| WHICH THEY HAVE ALREADY DONE. CORRECTIVE ACTION WILL BE TO RECALIBRATE THE |
| SETPOINTS. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. |
| |
| * * * UPDATE 1653 8/11/1999 FROM PALMER TAKEN BY STRANSKY * * * |
| |
| "This is a followup notification to our report made at 1040 this morning. |
| The nonconservative setpoints for the containment ventilation isolation |
| function from the four containment area radiation monitors has been |
| corrected. The setpoints were corrected and the area radiation monitors |
| declared operable at 1225 today. We are still investigating if this was an |
| actual 'loss of a safety function'. Followup notification will be provided |
| in the applicable 10 CFR 50.73 notification." |
| |
| The NRC resident inspector will be informed of this update by the licensee. |
| Notified R2DO (Ogle). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36015 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 08/11/1999|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 12:04[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 08/11/1999|
+------------------------------------------------+EVENT TIME: 09:25[CDT]|
| NRC NOTIFIED BY: DAVE NETERER |LAST UPDATE DATE: 08/11/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DALE POWERS R4 |
|10 CFR SECTION: |ROBERT BENNEDICT NRR |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION |FRANK CONGEL IRO |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO HEATER DRAIN LINE BREAK |
| |
| Operators manually tripped the reactor after receiving indication of a steam |
| leak in the turbine building. An 8" diameter line from the 'D' 1st stage |
| reheater drain tank to the '6B' high pressure heater experienced a double |
| ended guillotine break. All control rods inserted into the core following |
| the trip, and all systems functioned as designed. The licensee reported that |
| the unit is currently stable in Hot Standby, and the steam leak has been |
| isolated. No personnel injuries resulted from this event. |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36016 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 08/11/1999|
| UNIT: [] [2] [] STATE: NY |NOTIFICATION TIME: 13:43[EDT]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 08/11/1999|
+------------------------------------------------+EVENT TIME: 10:06[EDT]|
| NRC NOTIFIED BY: BRIAN WEAVER |LAST UPDATE DATE: 08/11/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |HAROLD GRAY 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INADVERTENT DIESEL GENERATOR START DURING TROUBLESHOOTING OF A SPEED CONTROL |
| PROBLEM |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On 08/11/99 at 1006, Nine Mile Point Unit 2 experienced an inadvertent |
| start of the Division I Diesel Generator during troubleshooting of a speed |
| control problem. This speed control problem had been experienced earlier |
| when the Diesel no-load frequency could not be controlled from the control |
| room when the Diesel was started for the monthly surveillance/PMT run. The |
| Division I Diesel has been inoperable since 0710 on 08/10/99 for preplanned |
| maintenance." |
| |
| "The primary starting circuit relay 4X1 had already been diagnosed with high |
| resistance readings across shut contacts indicating that it needed |
| replacement. Further troubleshooting was desired to ensure the remainder of |
| the primary starting circuit was operating correctly prior to restarting the |
| Diesel. The primary starting circuit relay 4X1 was removed from the circuit |
| and a test meter was placed on the coil inputs for the 4X1 relay to monitor |
| coil voltage when the DS9 optical isolator receiver was actuated by a |
| flashlight. This action allowed testing of the optical isolator receiver |
| board 'E' without inducing an engine start. The fact that board 'A' DS11 |
| optical isolator receiver would also turn on was missed during the planning |
| of the emergent work order. The DS11 optical isolator activation caused a |
| secondary start signal to be generated which initiated the inadvertent |
| Diesel start." |
| |
| "This notification is being made per 10CFR50.72 (b)(2)(ii) for 'any event or |
| condition that results in a manual or automatic actuation of any Engineered |
| Safety Feature.' Although the actuation was invalid, the actuation was not |
| pre-planned, and the Diesel was not removed from service." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36017 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/11/1999|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 14:08[EDT]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/11/1999|
+------------------------------------------------+EVENT TIME: 13:53[EDT]|
| NRC NOTIFIED BY: KEN TRUESDALE |LAST UPDATE DATE: 08/11/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| DISCOVERY OF A HISTORICAL CONDITION INVOLVING LOW DIESEL GENERATOR VOLTAGE |
| |
| The licensee determined that voltage for the 'B' emergency diesel generator |
| would not have met the technical specification criteria, and this rendered |
| the 'B' emergency diesel generator inoperable approximately 32 days prior to |
| 08/05/99. Although the voltage was discovered to be low during a test run |
| of the 'B' emergency diesel generator on 08/05/99, it was thought to be |
| acceptable (satisfactory) at the time of the test run. However, subsequent |
| engineering review determined that the voltage was in fact below the |
| technical specification acceptance criteria. |
| |
| The licensee determined this event to be reportable at 1353 on 08/11/99. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36018 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/11/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:46[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/10/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:00[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/11/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS R3 |
| DOCKET: 0707002 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JIM McCLEERY | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FAILURE OF 13 HIGH PRESSURE FIRE WATER SPRINKLER SYSTEMS TO MEET SYSTEM |
| OPERABILITY REQUIREMENTS (24-Hour Report) |
| |
| The following text is a portion of a facsimile received from Portsmouth: |
| |
| "On 08/10/99 at approximately 1600 hours, the Plant Shift Superintendent |
| (PSS) was notified that 13 sprinkler systems associated with the High |
| Pressure Fire Water (HPFW) system were not capable of meeting system |
| operability requirements. This condition was discovered as a result of an |
| engineering review of individual sprinkler heads that had previously been |
| identified as exhibiting corrosion around the valve seat. The engineering |
| review was conducted following the discovery that similar corrosion problems |
| experienced at the Paducah Gaseous Diffusion Plant resulted in sprinkler |
| heads being unable to actuate at normal pressure. An initial screening of |
| PORTS sprinkler heads known to exhibit corrosion was conducted, and systems |
| where the potential for two or more adjacent heads to be corroded were |
| inspected. This identified 11 systems in the X-333 and 2 systems in the |
| X-326 that did not meet the sprinkler system operability requirement that no |
| two adjacent sprinkler heads be inoperable." |
| |
| "The PSS declared the affected sprinkler systems inoperable, and TSR |
| required actions were completed. Further inspections of sprinkler systems |
| are planned. This report will be updated if additional sprinkler systems |
| are determined to be inoperable." |
| |
| "There was no loss of hazardous/radioactive material or |
| radioactive/radiological contamination exposure as a result of this |
| event." |
| |
| Portsmouth personnel notified the NRC resident inspector as well as the |
| onsite Department of Energy representative. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36019 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 08/11/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 15:12[EDT]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 08/11/1999|
+------------------------------------------------+EVENT TIME: 15:00[EDT]|
| NRC NOTIFIED BY: MIKE MICKLOW |LAST UPDATE DATE: 08/11/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
|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
+------------------------------------------------------------------------------+
| DISCOVERY THAT ONE OF SIX RESIDUAL HEAT REMOVAL (RHR) PUMP ANCHOR BOLTS WAS |
| MISSING |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During [an] engineering walkdown of [the] 'B' RHR pump, it was determined |
| that (1) corner anchor bolt was missing out of a total of (6) anchor bolts. |
| Preliminary analysis indicates that [the] existing anchorage configuration |
| cannot be seismically qualified." |
| |
| The unit is in a 72-hour limiting condition for operation as a result of |
| this issue. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36020 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 08/11/1999|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 16:34[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 08/11/1999|
+------------------------------------------------+EVENT TIME: 15:33[CDT]|
| NRC NOTIFIED BY: DAVID CLARIDGE |LAST UPDATE DATE: 08/11/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DALE POWERS R4 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| VCT OUTLET VALVES DO NOT MEET 10 CFR 50, APPENDIX R SEPARATION REQUIREMENT |
| |
| The volume control tank (VCT) outlet valves (BG-LCV-1112B and C) are located |
| approximately 42" apart, and are not separated by a three hour rated fire |
| barrier. A postulated fire in this area could prevent these valves from |
| being closed. The valves are normally open to provide a suction source for |
| the centrifugal charging pumps. The postulated fire could prevent the VCT |
| from being isolated from the CCP suction, permitting the hydrogen cover gas |
| in the VCT to enter the suction of the CCPs, damaging the pumps and causing |
| the loss of high head safety injection. In addition, the VCT level |
| transmitters associated with the above mentioned valves are not separated by |
| a fire barrier, and are less than 20 feet apart. A postulated fire could |
| damage both level transmitters, preventing the VCT from isolating upon low |
| level. |
| |
| The licensee considers this condition to be outside the design basis of the |
| plant for fire protection of safe shutdown components. A continuous fire |
| watch has been posted, and, in the event of a fire, actions will be taken to |
| isolate the VCT. If these actions are not successful, the boric acid |
| transfer pump will be started to provide a water source to the CCPs to |
| prevent hydrogen intrusion into the CCP suction. The licensee is currently |
| working to find a permanent solution to this condition. |
| |
| The NRC resident inspector will be informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36021 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/11/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 21:51[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/11/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:50[CDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/11/1999|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |BRUCE BURGESS R3 |
| DOCKET: 0707001 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KEVIN BEASLEY | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| GASEOUS DIFFUSION REPORT - UF6 DETECTION SYSTEM RENDERED INOPERABLE |
| |
| "At 1350, on 8/11/99. maintenance personnel were in the process of |
| completing repairs to valves in the C-333-A feed facility. During this work, |
| a pressure indicator was bumped by the maintenance personnel causing a |
| spark, which shorted out the fuse to the #1 North and South autoclaves power |
| supply. The power supply, for the local autoclave area audible and visual |
| alarms for the UF6 Release Detection System are fed from the #1 autoclaves |
| control power. Due to the loss of control power to the #1 autoclaves, the |
| UF6 Release Detection System was rendered inoperable. At the time of this |
| incident, the C-333-A facility was in an operational mode in which the UF6 |
| Release Detection System was required to be operable. Limiting Conditions |
| for Operation (LCO) required actions were put in place until power could be |
| restored. Power was restored, and the UF6 Release Detection was operable at |
| 1715 on 8/11/98. |
| |
| "It has been determined that this event is reportable under |
| 10CFR76.120(c)(2) as an event in which equipment is disabled or fails to |
| function as designed." |
| |
| The NRC resident inspector has been informed of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36022 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/12/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 01:30[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/11/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 12:35[EDT]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/12/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |BRUCE BURGESS R3 |
| DOCKET: 0707002 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SPAETH | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24 HOUR 91-01 BULLETIN RESPONSE |
| |
| On 8/11/99 at 1235 hrs the Plant Shift Superintendent(PSS) was notified that |
| a Nuclear Criticality Safety Approval (NCSA) requirement was not being |
| maintained in the X-333 process building. NCS Engineering, while performing |
| a Pre-implementation walkdown of an NCSA, noticed a depression in the floor |
| around a building column (X-333 operating floor) that is greater than 1.5 |
| inches deep (approx. 1.75 to 2 inches). A 12-position rack for storing |
| small diameter uranium bearing containers is located directly above the |
| depression. (NCSA-PLANT025) |
| |
| Requirement #10 of NCSA-PLANT025.A01 states in part, "Storage areas shall |
| not be located over equipment or spaces that could confine a spill to a |
| depth of greater than 1.5 inches. In the event of a spill or a loss of |
| container integrity, the depression in the floor (a violation of requirement |
| #10) could result in an unfavorable geometry." |
| |
| At the direction of the Plant Shift Superintendent the requirements for an |
| NCS anomalous condition were initiated and the area bounded off. |
| |
| Safety significance of the event is low and the diked area would have to be |
| full of uranium at optimum moderated conditions for criticality to be |
| possible. Geometry was the controlled parameter that was lost. The mass of |
| material (uranium solution with a max allowed enrichment of 10%) is not |
| controlled therefore more than a safe mass could be in the containers. |
| |
| Corrective action was to remove all small containers from the storage area |
| and reestablish NCS compliance. |
| |
| There was no loss of hazardous/radioactive material or |
| radioactive/radiological contamination exposure as a result of this event. |
| |
| The NRC Resident Inspector was notified. |
| |
| The DOE Representative will be notified. |
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Page Last Reviewed/Updated Thursday, March 25, 2021