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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. | +------------------------------------------------------------------------------+