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Event Notification Report for November 29, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/26/1999 - 11/29/1999
** EVENT NUMBERS **
36464 36465 36466 36467 36468 36469 36470 36471
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36464 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/26/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 06:46[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/26/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 03:00[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/26/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |RONALD GARDNER R3 |
| DOCKET: 0707002 |BRIAN SMITH NMSS |
+------------------------------------------------+FRANK CONGEL IRO |
| NRC NOTIFIED BY: RON CRABTREE | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01 RESPONSE (4-HOUR REPORT) - LOSS OF SPACING AND MODERATION |
| CONTROLS |
| |
| The following text is a portion of a facsimile received from Portsmouth: |
| |
| "On 11/26/99 at 0341 hours, the Plant Shift Superintendent (PSS) was |
| notified that NCSA-PLANT062.A02 Nuclear Criticality Safety Approval (NCSA) |
| requirements were not being met. A conical section of pipe removed during |
| maintenance activities on cell 33-5-10 was staged less than 2 feet from |
| other uranium-bearing piping in the cell housing. It was also identified |
| that the flanged openings of the conical transition piece were not covered |
| as required by NCSA-PLANT062.A02. [These issues were discovered at 0300 |
| hours.]" |
| |
| "This violated requirement #3 of NCSA-PLANT062.A02, which states in part: |
| 'Both favorable and unfavorable types of uncomplicated handling (UH) |
| equipment shall be spaced a minimum of 2 feet edge-to-edge from other |
| uranium-bearing equipment.' Requirement #4, which states that |
| openings/penetrations made during maintenance activities shall be covered to |
| minimize the potential for moderator collection and moist air exposure when |
| unattended, was also violated." |
| |
| "This is reportable under NRC Bulletin 91-01, 4-hour criticality control." |
| |
| "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 and plan to notify |
| the Department of Energy site representative. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36465 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 11/26/1999|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 09:12[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 11/26/1999|
+------------------------------------------------+EVENT TIME: 08:00[EST]|
| NRC NOTIFIED BY: DAVE WILLIAMS |LAST UPDATE DATE: 11/26/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LEN WERT R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING A LIVE SEA TURTLE REMOVED FROM THE INTAKE |
| CANAL BARRIER NET |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At approximately 0730 on 11/26/99, a live juvenile loggerhead sea turtle |
| was removed from the barrier net in the common plant intake canal. The |
| Florida Department of Environmental Protection was notified at approximately |
| 0800 for transfer to a rehabilitation facility." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36466 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 11/26/1999|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 17:16[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 11/26/1999|
+------------------------------------------------+EVENT TIME: 12:27[CST]|
| NRC NOTIFIED BY: GARY OLMSTEAD |LAST UPDATE DATE: 11/26/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BLAIR SPITZBERG R4 |
|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 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| Unit experienced an automatic reactor trip following a momentary loss of |
| power to an I&C power supply that resulted in a low Steam Generator water |
| level. |
| |
| "This event is being reported in accordance with 10CFR50.72(b)(2)(ii) due to |
| an automatic Reactor Trip and subsequent Aux Feedwater actuation and |
| Feedwater isolation: |
| |
| "On 11/26/99 at 1227 CST with Callaway plant at 100% reactor power, a |
| Reactor Trip occurred on low Steam Generator 'A' level due to an apparent |
| momentary loss of power in Control Cabinet [Relay Panel] RP043. At 1204, |
| annunciator 93A 'Power Control System (PCS) Power Failure' alarmed due to a |
| failed RP043 primary power supply. Initial investigation revealed a failed |
| fuse in the RP043 primary power supply. The secondary power supply |
| immediately picked up load without incident. |
| |
| "Subsequent to the primary power supply failure, I&C technicians were sent |
| to the RP043 cabinet and the Primary Equipment Operator was sent to RP043 |
| supply breaker PG19GCR218 to investigate. During this investigation, Main |
| Feedwater Regulating valve [MFRV] 'A' went shut and both Main Feedwater |
| Pumps [MFPs] went to their low speed stops. Attempts by the Reactor |
| Operator to take manual control of 'A' MFRV and the MFPs were unsuccessful |
| resulting in the aforementioned Reactor Trip. |
| |
| "Discussions with I&C personnel stationed at RP043 indicated the secondary |
| power supplies appeared energized throughout the event. Discussions with |
| the Primary EO indicated he checked PG19GCR218 in the closed position |
| coincident with the trip. Plant personnel are currently investigating |
| PG19GCR218 and the apparent momentary loss of power to RP043. The plant is |
| currently stable in Mode 3 with RCS pressure at 2237 psig and RCS |
| temperature at 557.8 F. |
| |
| "Additional information: The NRC Senior Resident Inspector was contacted at |
| 1310 and responded to the Control Room." |
| |
| Auxiliary Feedwater is currently supplying the Steam Generators with steam |
| flow to the Main Condenser for decay heat removal. All control rods fully |
| inserted. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36467 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 11/26/1999|
| UNIT: [1] [2] [] STATE: FL |NOTIFICATION TIME: 17:34[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 11/26/1999|
+------------------------------------------------+EVENT TIME: 17:12[EST]|
| NRC NOTIFIED BY: DAVE WILLIAMS |LAST UPDATE DATE: 11/26/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LEN WERT R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO STATE AGENCY REGARDING DEAD SEA TURTLE FOUND IN |
| BARRIER NET OF THE INTAKE CANAL |
| |
| "[A] NOTIFICATION [WAS] MADE TO [THE] FLORIDA DEPARTMENT OF ENVIRONMENTAL |
| PROTECTION (DEP) REGARDING [THE] REMOVAL OF [A] DEAD SUB-ADULT LOGGERHEAD |
| SEA TURTLE FROM THE BARRIER NET IN THE COMMON PLANT INTAKE CANAL. THE |
| TURTLE WAS REMOVED AT APPROXIMATELY 1700 [HOURS] ON 11/26/99, AND THE |
| FLORIDA DEP WAS NOTIFIED AT 1710 HOURS. [THE] ANIMAL WAS FOUND WITH |
| MONOFILAMENT FISHING LINE AROUND [THE] FRONT FLIPPERS AND [THE] MORTALITY IS |
| NOT BELIEVED TO BE CAUSALLY RELATED TO PLANT OPERATIONS. THE LICENSEE WILL |
| NOTIFY THE NRC RESIDENT INSPECTOR." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 36468 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: FAIRVIEW SOUTHDALE HOSPITAL |NOTIFICATION DATE: 11/26/1999|
|LICENSEE: FAIRVIEW SOUTHDALE HOSPITAL |NOTIFICATION TIME: 23:46[EST]|
| CITY: EDINA REGION: 3 |EVENT DATE: 11/25/1999|
| COUNTY: STATE: MN |EVENT TIME: 07:05[CST]|
|LICENSE#: 22-00015-02 AGREEMENT: N |LAST UPDATE DATE: 11/26/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |RONALD GARDNER R3 |
| |JOE HOLONICH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DR. L. LEWANOWSKI | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FEMALE PATIENT RECEIVED LESS THAN THE PRESCRIBED DOSE DUE TO TECHNICIAN |
| ERROR |
| |
| A FEMALE PATIENT UNDERGOING TREATMENT FOR ENDOMETRIAL CANCER RECEIVED 5072 |
| RATHER THAN THE 6500 CENTIGRAY PRESCRIBED DUE TO TECHNICIAN ERROR IN LOADING |
| TWO (2) OLD CESIUM-137 SOURCES INTO THE APPLICATOR. THE NEWER SOURCES (25 |
| MILLIGRAMS RADIUM EQUIVALENT EACH) WERE CLEARLY LABELED AND INDICATED ON THE |
| HOSPITAL FORMS. THE PRESCRIBING PHYSICIAN WAS INFORMED AND REQUESTED THAT |
| THE PATIENT NOT BE NOTIFIED PENDING AN EVALUATION OF WHETHER ADDITIONAL |
| TREATMENT IS REQUIRED. THE LICENSEE WILL SUBMIT A WRITTEN REPORT WITHIN |
| FIFTEEN DAYS. |
| |
| CALLTHE HEADQUARTERS OPERATIONS OFFICER FOR CONTACT INFORMATION. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36469 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 11/27/1999|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 07:00[EST]|
| RXTYPE: [3] CE |EVENT DATE: 11/27/1999|
+------------------------------------------------+EVENT TIME: 05:33[CST]|
| NRC NOTIFIED BY: P. BOCSKOV/B. LIETZKE |LAST UPDATE DATE: 11/27/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: ALE |BLAIR SPITZBERG R4 |
|10 CFR SECTION: |ELINOR ADENSAM NRR |
|AAEC 50.72 (a) (1) (I) EMERGENCY DECLARED |FRANK CONGEL IRO |
| |THOMAS MCKENNA RCT |
| |SUE GAGNER OPA |
| |KEN CIBOCH FEMA |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N N 0 Hot Shutdown |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - ALERT DUE TO SUDDEN DEPRESSURIZATION OF RCS AND LOSS OF 3000 GALLONS FROM |
| RCS - |
| |
| ON 11/26/99, WATERFORD WAS SHUT DOWN FROM 100% POWER TO REPAIR A LEAK ON A |
| MAIN STEAM LINE DRAIN LINE. |
| |
| AT 0500 CST ON 11/27/99, WITH THE PLANT IN MODE 4 (HOT SHUTDOWN), THE |
| LICENSEE OPENED THE SUCTION VALVE (#SI-407B) TO THE TRAIN 'B' LOW PRESSURE |
| SAFETY INJECTION PUMP TO PLACE THE PLANT ON SHUTDOWN COOLING. CONTROL ROOM |
| OPERATORS HEARD A LOUD NOISE. APPROXIMATELY 3000 GALLONS DRAINED FROM THE |
| REACTOR COOLANT SYSTEM (RCS) INTO THE REFUELING WATER STORAGE POOL IN ABOUT |
| 2 MINUTES. THE WATER LEVEL IN THE PRESSURIZER DROPPED FROM 35% TO 0%. THE |
| PRESSURIZER HEATERS TRIPPED. RCS PRESSURE DROPPED FROM 350 PSIG TO 100 |
| PSIG. RCS TEMPERATURE REMAINED AT 295þF. THE LICENSEE CLOSED THE VALVE |
| WHICH STOPPED THE DRAIN FROM THE RCS AND REFILLED THE PRESSURIZER TO 53% |
| USING THE HIGH PRESSURE SAFETY INJECTION PUMP. |
| |
| AT 0533 CST ON 11/27/99, THE LICENSEE DECLARED AN ALERT DUE TO A |
| PRECAUTIONARY STATEMENT IN THE EMERGENCY OPERATING PROCEDURE DUE TO THE |
| SUDDEN DEPRESSURIZATION OF THE RCS. THE LICENSEE NOTIFIED STATE AND LOCAL |
| OFFICIALS AND THE NRC SENIOR RESIDENT INSPECTOR. THE LICENSEE CALLED |
| PERSONNEL TO COME TO THE PLANT TO STAFF THEIR EMERGENCY OPERATIONS FACILITY |
| AND TECHNICAL SUPPORT CENTER AND ACTIVATED THEIR EMERGENCY RESPONSE DATA |
| SYSTEM. |
| |
| THE PLANT IS IN NATURAL CIRCULATION TO STEAM GENERATOR (S/G) #2 TO THE MAIN |
| CONDENSER. S/G #1 IS INOPERABLE. THERE WAS NO RELEASE OF RADIATION AND NO |
| PERSONNEL WERE INJURED. |
| |
| AT 0640 CST ON 11/27/99, THE NRC ENTERED THE MONITORING PHASE OF NORMAL |
| RESPONSE MODE. NRC REGION 4 STAFFED THEIR INCIDENT RESPONSE CENTER. THE |
| LICENSEE IS PREPARING A PRESS RELEASE. |
| |
| THE PLANT IS STABLE IN MODE 4 (HOT SHUTDOWN). |
| |
| SUBSEQUENTLY, THE LICENSEE DISCOVERED THAT A 6 INCH MANUAL RECIRC VALVE |
| (#SI-417B) WAS OPEN, BUT WAS INDICATING CLOSED. THE REACH ROD TO THE VALVE |
| WAS BROKEN. THE LICENSEE DETERMINED THAT THE VALVE HAD BEEN OPEN FOR ABOUT |
| A WEEK. |
| |
| AT 1100 EST ON 11/27/99, A COMMISSIONERS' ASSISTANTS BRIEFING WAS HELD WITH |
| THE FOLLOWING ATTENDEES: IRO FRANK CONGEL, JOE GIITTER; NRR PROJECT |
| DIRECTOR STU RICHARDS; OPA BETH HAYDEN; OSP PAUL LOHAUS; OIP RON HAUBER; OCA |
| LAURA GERKE; EDO DAVE LANGE; DEDMRS PAPERIELLO; SECY ANNETTE VIETTI-COOK; |
| CHAIRMAN MESERVE (GLEN TRACY); COMM DICUS (TOM HILTZ); COMM McGAFFIGAN |
| (JANET SCHLUETER); COMM DIAZ (TONY HSIA); COMM MERRIFIELD (BRIAN McCABE); |
| REGION 4 TOM ANDREWS, CHRIS KENNEDY, ELLIS MERSCHOFF, KEN BROCKMAN |
| (BRIEFER); SRI TOM FARNHOLTZ. |
| |
| * * * UPDATE AT 1335 EST ON 11/27/99 FROM MIKE MASON TO S. SANDIN * * * |
| |
| THE LICENSEE EXITED THE ALERT AT 1226 CST AFTER VERIFYING THAT THE PLANT WAS |
| IN MODE 5 AND STABLE (TERMINATION CRITERIA). THE LICENSEE INFORMED |
| STATE/LOCAL AGENCIES AND THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS |
| OFFICER NOTIFIED R4(MERSCHOFF), EO(ADENSAM), IRO(CONGEL), PAO(GAGNER, |
| JASINSKI), EDO(PAPERIELLO), CHAIRMAN MESERVE(TRACY), FEMA(SULLIVAN), |
| DOE(YOUNG), EPA(DiGIORGIO), USDA(CONLEY) AND HHS(BERGER). |
| |
| AT 1345 EST THE NRC EXITED THE MONITORING PHASE OF NORMAL RESPONSE MODE PER |
| A 1315 EST CONFERENCE CALL INVOLVING R4(MERSCHOFF), NRR(COLLINS, RICHARDS), |
| IRO(CONGEL) AND EDO(TRAVERS). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36470 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 11/28/1999|
| UNIT: [1] [] [] STATE: IA |NOTIFICATION TIME: 02:13[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 11/27/1999|
+------------------------------------------------+EVENT TIME: 22:35[CST]|
| NRC NOTIFIED BY: DAVE SCHUSSLER |LAST UPDATE DATE: 11/28/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RONALD GARDNER R3 |
|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 Y 1 Startup |1 Startup |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - SAFETY/RELIEF VALVE OPENED FOR 1 MINUTE DURING MAINTENANCE ACTIVITIES - |
| |
| DURING A REACTOR STARTUP WITH REACTOR AT 1% POWER, MAINTENANCE TECHNICIANS |
| WERE PREPARING TO PERFORM AN INSPECTION ON THE 125 VDC DIVISION I ELECTRICAL |
| DISTRIBUTION SYSTEM BY USING A SCOUT GROUND DETECTION DEVICE TO TROUBLESHOOT |
| A SYSTEM GROUND. DURING THE MAINTENANCE INSPECTION, THE SCOUTING DEVICE |
| CAUSED SAFETY/RELIEF VALVE (SRV) (#PSV-4402) (ADS VALVE) TO OPEN AS |
| INDICATED BY "TAILPIPE HI TEMP" ALARM. THE OPENING OF THE SRV CAUSED THE |
| REACTOR VESSEL WATER LEVEL TO SWELL FROM A NORMAL LEVEL OF 190 INCHES TO 200 |
| INCHES. OTHER ALARMS ASSOCIATED WITH THE TROUBLESHOOTING WERE ALSO RECEIVED |
| IN THE CONTROL ROOM. MAINTENANCE ACTIVITIES ON 125 VDC DIVISION I |
| ELECTRICAL DISTRIBUTION SYSTEM WERE QUICKLY HALTED AND THE SRV COMPLETELY |
| CLOSED ABOUT ONE MINUTE AFTER OPENING CAUSING THE REACTOR VESSEL WATER LEVEL |
| TO DROP TO 178 INCHES. THE CONDENSATE SYSTEM WAS USED TO RESTORE WATER LEVEL |
| TO ITS NORMAL LEVEL OF 186 TO 195 INCHES. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36471 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 11/28/1999|
| UNIT: [1] [] [] STATE: MI |NOTIFICATION TIME: 19:50[EST]|
| RXTYPE: [1] CE |EVENT DATE: 11/28/1999|
+------------------------------------------------+EVENT TIME: 15:45[EST]|
| NRC NOTIFIED BY: DALE ENGLE |LAST UPDATE DATE: 11/28/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |RONALD GARDNER R3 |
|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
+------------------------------------------------------------------------------+
| "B" TRAIN LOW PRESSURE SAFETY INJECTION (LPSI) FLOW RATES FOUND DEGRADED |
| DURING SURVEILLANCE TESTING. |
| |
| "WHILE PERFORMING QO-8B (LOW PRESSURE SAFETY INJECTION FLOW TESTING), IT WAS |
| DETERMINED THAT FLOW TO TWO (2) OF FOUR (4) LOOPS (VALVES-MO-3012 & MO-3014 |
| [RIGHT CHANNEL]) WAS INADEQUATE. THE FLOW RATES WERE BELOW THE DESIGN BASIS |
| FOR ACCIDENT CONDITIONS. [THIS] CONDITION WAS DISCOVERED DURING |
| SURVEILLANCE TESTING WHILE THE PLANT WAS IN COLD SHUTDOWN. THIS IS |
| REPORTABLE PER 50.72(b)(2)(I)." |
| |
| THE DESIGN FLOW RATE IS 1720 GPM. THE AS-FOUND FLOW RATES THROUGH VALVES |
| 3012 & 3014 WERE 1650 AND 1500 GPM, RESPECTIVELY. THE "B" TRAIN LPSI HAS |
| BEEN DECLARED INOPERABLE PENDING CORRECTIVE ACTION WHICH IS TO BE |
| DETERMINED. THE UNIT IS NOT IN A TECH SPEC ACTION STATEMENT IN THAT LPSI IS |
| NOT REQUIRED FOR CURRENT PLANT CONDITIONS. THE SURVEILLANCE TEST WHICH |
| IDENTIFIED THIS CONDITION IS PERFORMED EACH REFUELING OUTAGE (APPROXIMATELY |
| EVERY 18 MONTHS). THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+