Event Notification Report for January 19, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/15/1999 - 01/19/1999
** EVENT NUMBERS **
34914 35251 35265 35267 35268 35269 35270 35271 35272 35273 35274 35275
35276 35277 35278 35279 35280
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 34914 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: COOPER ENERGY SERVICES |NOTIFICATION DATE: 10/14/1998|
|LICENSEE: COOPER ENERGY SERVICES |NOTIFICATION TIME: 15:05[EDT]|
| CITY: GROVE CITY REGION: 1 |EVENT DATE: 10/13/1998|
| COUNTY: STATE: PA |EVENT TIME: 00:00[EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 01/15/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CURT COWGILL R1DO |
| | |
+------------------------------------------------+VERN HODGE/RPM/PCEB NRR |
| NRC NOTIFIED BY: TED MILLER | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 10 CFR PART 21 NOTIFICATION - AIR START DISTRIBUTOR FILTER MICRON RATING |
| EVALUATION AND INTERIM REPORT - ENTERPRISE DSR-4 AND DSRV-4 EMERGENCY |
| DIESEL ENGINE |
| |
| THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM COOPER ENERGY |
| SERVICES: |
| |
| "OUR INVESTIGATION IS OF A STARTING AIR DISTRIBUTOR FILTER ELEMENT PROVIDED |
| AS REPLACEMENT PART COMPONENTS FOR THE ENTERPRISE R4 AND RV4 EMERGENCY |
| DIESEL GENERATOR SYSTEM. THE COOPER-BESSEMER PART NUMBER OF THE FILTER |
| CARTRIDGE IS SB-006-002." |
| |
| "DISCUSSION:" |
| |
| "DURING THE COMMERCIAL GRADE DEDICATION PROCESS, FILTER ELEMENTS FROM |
| MULTIPLE SUPPLIERS WERE PULLED FROM STORES AND INSPECTED FOR NUCLEAR |
| SAFETY-RELATED APPLICATION. THE VARIATION IN THE COLOR AND THE LACK OF SOME |
| FILTER ELEMENTS HAVING THE MICRON RATING STAMPED ON THEM PROMPTED AN |
| INVESTIGATION AS TO THE ACTUAL MICRON RATING." |
| |
| "WE ARE IN THE PROCESS OF PERFORMING INDEPENDENT LAB TESTING TO ASCERTAIN |
| WHETHER FILTER ELEMENTS OF AN INCORRECT MICRON RATING HAVE BEEN PROVIDED TO |
| ANY OF OUR NUCLEAR CUSTOMERS. IT IS EXPECTED THAT THIS EVALUATION WILL BE |
| COMPLETED ON OR BEFORE NOVEMBER 30, 1998." |
| |
| - - - - - - - - - - - - - UPDATE AT 1545 ON 11/25/98 VIA FACSIMILE RECEIVED |
| BY TROCINE - - - - - - - - - - - - - - |
| |
| THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM COOPER ENERGY |
| SERVICES: |
| |
| "WE ARE CONTINUING THE PROCESS OF PERFORMING INDEPENDENT LAB TESTING TO |
| ASCERTAIN WHETHER FILTER ELEMENTS OF AN INCORRECT MICRON RATING HAVE BEEN |
| PROVIDED TO ANY OF OUR NUCLEAR CUSTOMERS. IT IS EXPECTED THAT THIS |
| EVALUATION WILL BE COMPLETED ON OR BEFORE JANUARY 15, 1999." |
| |
| THE NRC OPERATIONS OFFICER NOTIFIED NRR/RPM/PCEB (HODGE) AS WELL AS THE R1DO |
| (DELLA GRECA), R2DO (MCALPINE), R3DO (LEACH), AND R4DO (SANBORN). (CONTACT |
| THE NRC OPERATIONS CENTER FOR COOPER ENERGY SERVICES CONTACT NAMES AND |
| TELEPHONE NUMBERS.) |
| |
| ********************UPDATE AT 1023 ON 1/15/99 VIA FACSIMILE RECEIVED BY |
| WEAVER ********************* |
| |
| "During the commercial grade dedication process, filter elements from |
| multiple suppliers were pulled from stores and inspected for nuclear safety |
| related application. The variation in the color and the fact that some |
| filter elements did not have the supplier part number stamped on them |
| prompted an investigation as to the actual micron rating. |
| |
| "Our evaluation of the subject starting air distributor filter elements |
| (SB-006-002) that were in questions is complete. It is Cooper Energy |
| Services' judgement that this does not fall under the Title 10 CFR Part 21 |
| criteria. Evaluation of the suspect filter elements, as compared to the |
| known previously qualified element, was accomplished by subjecting an |
| element of each to identical testing, which showed that the suspect element |
| performs as well as the previously qualified element. Cooper Energy Services |
| believes this to be an isolated case, but further investigations are |
| continuing to be conducted via our in-house corrective action program for |
| transportability concerns." |
| |
| The Operations Officer notified Vern Hodge (NRR) by fax. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 35251 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: TEXAS DEPARTMENT OF HEALTH |NOTIFICATION DATE: 01/13/1999|
|LICENSEE: GLOBAL X-RAY |NOTIFICATION TIME: 10:58[EST]|
| CITY: REGION: 4 |EVENT DATE: 12/31/1998|
| COUNTY: STATE: TX |EVENT TIME: 18:00[CST]|
|LICENSE#: L-3663 AGREEMENT: Y |LAST UPDATE DATE: 01/15/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BLAIR SPITZBERG R4 |
| |DON COOL, NMSS EO |
+------------------------------------------------+FRANK CONGEL IRD |
| NRC NOTIFIED BY: FACSIMILE | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
|BAD1 20.2202(a)(1) PERS OVEREXPOSURE | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT REGARDING OVEREXPOSURE OF A GLOBAL X-RAY TRAINEE (10 |
| REM WHOLE BODY AND EXTREMITY HIGH ENOUGH TO CAUSE INJURY) |
| |
| The following text is a portion of a facsimile received from the Texas |
| Department of Health: |
| |
| "10 CFR Part 20.2202(a)(1) - Exposure (real or threatened) [greater than or |
| equal to] TEDE of 25 rem, eye/lens 15 rem, skin/extremities 50 rads." |
| |
| "A Texas licensee - Global X-Ray had a trainee overexposure - [Whole Body |
| approximately equal to] 10 rem and extremity high enough to cause injury." |
| |
| There was no additional information available on the facsimile. |
| |
| (Call the NRC Operations Center for a contact telephone number and |
| address.) |
| |
| ***UPDATE AT 0908 EST ON 1/15/99 FROM BRADLEY CASKEY VIA FACSIMILE RECEIVED |
| BY TROCINE*** |
| |
| Reference: Incident file #7404 - Radiography Trainee Overexposure - Global |
| X-Ray - L-3663 |
| |
| At approximately 1100 CST on January 1, 1999, Global X-Ray (L-3663) called |
| the Texas Department of Health to report an incident that occurred the |
| previous evening (December 31, 1998) at approximately 1800 CST. A |
| radiography trainee was involved in an incident that had the potential of |
| being a significant overexposure (approximately 10 rem whole body and a |
| licensee-calculated finger exposure of approximately 800 millirem) involving |
| a 123-curie Iridium-192 source. On Tuesday January 5, 1999, representatives |
| from the Texas Department of Health met with representatives from the Global |
| X-Ray facility. |
| |
| The following text is a portion of a facsimile received from the Texas |
| Department of Health: |
| |
| "... On December 31, 1998, a radiographer and a radiographer trainee were |
| working with a 123-curie Iridium-192 radiography source at a temporary job |
| site when the trainee failed to retract the source into the shielded |
| position. A collimator was not being used because an elliptical shot was |
| being performed. As a result, the trainee was exposed to the source at |
| [the] end of the guide tube for approximately 4 minutes at a distance of |
| approximately 2 feet and touched the end cap where the source was located 3 |
| or 4 times for 2 or 3 seconds each time. [The] only shielding was from the |
| brass end cap. Symptoms of a radiation injury [appeared] on the index |
| finger of the right hand on January 10, 1999." |
| |
| "[The] radiographer and trainee were sent on the job by the office manager, |
| who had been told by the company president that the radiographer could act |
| as a trainer because the paperwork requesting he be named a trainer had been |
| mailed to the Bureau of Radiation Control." |
| |
| "[The] radiographer was new with the company, was not familiar with the |
| trainee he was [sent] out with, and did not know that he was not a |
| radiographer. [The] radiographer had been a trainer for several other |
| radiography companies and was familiar with the requirements of a trainer |
| working with a trainee." |
| |
| "[The] trainee thought they had finished work for the day and had taken his |
| tool belt off and put it in the truck. His dosimeter and alarming rate |
| meter was on his tool belt; therefore, he did not have [them] on when he was |
| reshooting two radiographs at the end of the day. He had an operating |
| survey meter but did not use it during the radiographs." |
| |
| "Calculations were made to approximate the whole body and finger extremity |
| exposures. [The] trainee was uncertain of the details of the incident and |
| was only able to give approximations... Whole body exposure calculations |
| were approximately 10 rem, and finger extremity exposure calculations were |
| 3,000 to 5,000 rem. [The] appearance of radiation injury symptoms 10 days |
| from the date of the incident supports the extremity calculations." |
| |
| The NRC operations officer notified the R4DO (Spitzberg), NMSS EO |
| (Surmeier), and IRD (Congel). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35265 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 01/14/1999|
| UNIT: [] [] [3] STATE: AL |NOTIFICATION TIME: 20:26[EST]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 01/14/1999|
+------------------------------------------------+EVENT TIME: 16:40[CST]|
| NRC NOTIFIED BY: RODNEY NACOSTE |LAST UPDATE DATE: 01/15/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) INOPERABLE DUE TO AN OIL LEAK |
| |
| THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: |
| |
| "DURING THE PERFORMANCE OF [PROCEDURE] 3-SR-3.5.1.7, HPCI MAIN AND BOOSTER |
| PUMP SET DEVELOPED HEAD AND FLOW RATE TEST, WHILE THE HPCI PUMP WAS |
| STARTING, AN OIL LEAK DEVELOPED ON [VALVE] 3-SV-73-18, HPCI STOP VALVE. ONE |
| STUD WAS FOUND SHEARED FROM THE STOP VALVE. HPCI WAS SUBSEQUENTLY DECLARED |
| INOPERABLE, AND THE APPROPRIATE [LIMITING CONDITIONS FOR OPERATION] WERE |
| ENTERED." |
| |
| THE LICENSEE IS CONDUCTING AN INVESTIGATION TO DETERMINE THE CAUSE OF THE |
| FAILURE AND THE APPROPRIATE CORRECTIVE ACTIONS. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE 1245 EST ON 1/15/99 FROM CHRIS VAUGHN TO S. SANDIN * * * |
| |
| THE LICENSEE AFTER FURTHER REVIEW CONCLUDED THAT THE APPLICABLE PARAGRAPH |
| FOR REPORTABILITY WAS 10CFR50.72(b)(2)(iii)(D) ACCIDENT MITIGATION RATHER |
| THAN 10CFR50.72(b)(2)(iii)(B) RHR CAPABILITY. THE LICENSEE INFORMED THE NRC |
| RESIDENT INSPECTOR. THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO (AL |
| BELISLE). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Research Reactor |Event Number: 35267 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NATIONAL INST OF STANDARDS & TECH |NOTIFICATION DATE: 01/15/1999|
| RXTYPE: 20000 KW TEST |NOTIFICATION TIME: 06:42[EST]|
| COMMENTS: |EVENT DATE: 01/15/1999|
| |EVENT TIME: 05:26[EST]|
| |LAST UPDATE DATE: 01/15/1999|
| CITY: GAITHERSBURG REGION: 1 +-----------------------------+
| COUNTY: MONTGOMERY STATE: MD |PERSON ORGANIZATION |
|LICENSE#: TR-5 AGREEMENT: N |GENE KELLY R1 |
| DOCKET: 05000184 |DAVID MATTHEWS/NRR EO |
+------------------------------------------------+FRANK CONGEL IRO |
| NRC NOTIFIED BY: AL TOTH |TED MICHAELS/NRR PM |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF COMMERCIAL OFFSITE POWER AND AUTOMATIC REACTOR SHUT DOWN |
| |
| There was a loss of commercial offsite power to the entire National |
| Institute of Standards site during a winter storm. As a result, the |
| National Bureau of Standards Reactor automatically shut down at 0526 on |
| 01/15/99. All four shim arms (safety blades) and the regulating rod fully |
| inserted. The emergency diesel generator started and is currently supplying |
| power. There is flow through the core with the primary D2O, and there is a |
| heat sink using a small secondary pump that supplies a cooling tower. Core |
| temperature is being maintained by cycling the small pump on and off. |
| |
| There was no emergency declared. It is currently anticipated that it will |
| be several hours before commercial power is restored. |
| |
| (Contact the NRC Operations Center for a site contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35268 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 01/15/1999|
| UNIT: [] [2] [] STATE: SC |NOTIFICATION TIME: 10:07[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/15/1999|
+------------------------------------------------+EVENT TIME: 09:44[EST]|
| NRC NOTIFIED BY: ED BREWER |LAST UPDATE DATE: 01/15/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|10 CFR SECTION: |ROBERT DENNIG/NRR EO |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |85 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO THE LOSS OF TWO AUXILIARY |
| FEEDWATER PUMPS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "[An] electrical failure [resulted] in the loss of auxiliary feedwater |
| suction swapover to [the] nuclear service water [system] rendering [two] |
| auxiliary feedwater pumps inoperable. Per [Technical Specification] |
| 3.7.2.1, with [two] auxiliary feedwater pumps inoperable, the unit must be |
| placed in Hot Standby within 6 hours and in Hot Shutdown within the |
| following 6 hours. [The] electrical failure also swapped controls for the |
| turbine-driven auxiliary feedwater pump to the local panel. |
| |
| "List of safety-related equipment not operational: [emergency core cooling |
| system] train 'B' due to '2B' safety injection pump [emergent work and] |
| control room ventilation train 'B' [due to planned maintenance]." |
| |
| The licensee is currently investigating this failure. There were no ongoing |
| maintenance or surveillance activities ongoing at the time of the event. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35269 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 01/15/1999|
| UNIT: [] [2] [3] STATE: AL |NOTIFICATION TIME: 11:12[EST]|
| RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 01/15/1999|
+------------------------------------------------+EVENT TIME: 06:30[CST]|
| NRC NOTIFIED BY: CHRIS VAUGHN |LAST UPDATE DATE: 01/15/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |AL BELISLE R2 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH CONTROL ROOM EMERGENCY VENTILATION TRAINS INOPERABLE FOR ABOUT 11 |
| HOURS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "EVENT DESCRIPTION: On 01/14/99 at 1305 [CST,] the Control Room Emergency |
| Ventilation (CREV) train 'B' was placed in service for flow rate testing |
| following scheduled replacement of the charcoal trays. At the time CREV |
| train 'B' was started, CREV train 'A' was the only operable CREV train. |
| When CREV 'B' was started, the CREV primary unit selector switch |
| (0-XSW-31-7214) was placed in the 'B' position. This in conjunction with |
| CREV 'B' in service for testing, rendered CREV 'A' incapable of |
| automatically starting on a valid initiation signal. Thus, both CREV trains |
| were inoperable from 1305 hours on 01/14/99 until 0008 hours on 01/15/99. |
| |
| "REPORTABILITY LOGIC: This condition is reportable per |
| 10CFR50.72(b)(2)(iii) as an event or condition that alone could have |
| prevented the fulfillment of the safety function of systems or structures |
| that are needed to mitigate the consequences of an accident. [A licensee |
| event report (LER)] is also required within 30 days per 10CFR50.73(a)(2)(v) |
| and (vi). |
| |
| "Additionally, Unit 2 and 3 Technical Specifications Section 3.7.3.D |
| requires [that Limiting Condition for Operation (LCO)] 3.0.3 be entered |
| immediately with two CREV subsystems inoperable. LCO 3.0.3 requires [that] |
| action be initiated within 1 hour to place the affected units in MODE 2 |
| within 7 hours. LCO 3.0.3 was not entered at the time both CREV subsystems |
| were inoperable. Therefore, this condition also requires submission of an |
| LER within 30 days per 10CFR50.73(a)(2)(i)(B), any operation or condition |
| prohibited by technical specifications." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35270 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 01/15/1999|
| UNIT: [] [2] [] STATE: CA |NOTIFICATION TIME: 13:21[EST]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 01/15/1999|
+------------------------------------------------+EVENT TIME: 06:30[PST]|
| NRC NOTIFIED BY: JORGE RODRIQUEZ |LAST UPDATE DATE: 01/15/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BLAIR SPITZBERG R4 |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N N 0 Refueling |0 Refueling |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| GREATER THAN 1% OF STEAM GENERATOR TUBES REQUIRE PLUGGING |
| |
| "This notification is being made in accordance with San Onofre Unit 2 |
| Technical Specification 5.5.2.11, 'Steam Generator Tube Surveillance |
| Program.' Table 5.5.2.11-1 of this specification requires SCE to provide |
| prompt notification to the NRC in accordance with 1OCFR5O.72 when one |
| percent or more of the inspected tubes in a steam generator are found |
| defective and require plugging or repair. |
| |
| "During the current Unit 2 Cycle 10 refueling outage, SCE is currently |
| inspecting 100 percent of the tubes in both Unit 2 steam generators. On |
| January I5, 1999, at 0630 PST, SCE determined that the number of defective |
| tubes in steam generator E-088 is greater than one percent of the total |
| tubes and require repair or plugging. The inspections are continuing and the |
| inspection results will be provided as required by Technical Specification |
| 5.7.2. |
| |
| " While the Technical Specifications require SCE to submit this report, the |
| condition itself does not meet the reporting criteria of 1OCFR5O.72. At the |
| time of this report, Unit 1 remains permanently shutdown and Unit 3 is |
| operating at about 100% power. |
| |
| "This report will be discussed with the NRC Resident Inspectors." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35271 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ABB COMBUSTION ENGINEERING |NOTIFICATION DATE: 01/15/1999|
|LICENSEE: ABB COMBUSTION ENGINEERING |NOTIFICATION TIME: 14:15[EST]|
| CITY: WINDSOR REGION: 1 |EVENT DATE: 01/15/1999|
| COUNTY: STATE: CT |EVENT TIME: 14:15[EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 01/15/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BLAIR SPITZBERG R4 |
| |VERN HODGE NRR |
+------------------------------------------------+ |
| NRC NOTIFIED BY: IAN RICKARD | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PART 21 NOTIFICATION RELATED TO MINIMUM CRITICAL POWER RATIO (MCPR) |
| |
| "The purpose of this letter is to notify the Nuclear Regulatory Commission |
| of a defect under 10 CFR 21, 'Reporting of Defects and Noncompliance.' The |
| defect concerns the Operating Limit for the Minimum Critical Power Ratio |
| (MCPR) in Boiling Water Reactors (BWRs) analyzed using the BISON fast |
| transient analysis code. Specifically, the defect involves incorrect |
| modeling of the reactor vessel lower plenum volume in the BISON code, which |
| could lead to the establishment of non-conservative MCPR Operating Limits in |
| plant technical specifications. |
| |
| "The Enclosure summarizes the evaluation performed by ABB Combustion |
| Engineering (ABB-CE). If you have any questions, please feel free to |
| contact me [Ian C. Rickard] or Virgil Paggen of my staff." |
| |
| This event effects WNP-2 current operating cycle (Cycle 14). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35272 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/15/1999|
| UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 14:17[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/15/1999|
+------------------------------------------------+EVENT TIME: 13:50[EST]|
| NRC NOTIFIED BY: NICK LAZZO |LAST UPDATE DATE: 01/15/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GENE KELLY R1 |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|3 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LICENSEE NOTIFIED THE NEW YORK STATE DEPARTMENT OF CONSERVATION OF A 1 QUART |
| TRANSMISSION OIL SPILL INTO THE STORM DRAIN SYSTEM |
| |
| "On January 15, 1999, at 1350 hours, a notification was made to the New York |
| State Department of Conservation (NYSDEC), Spill Report No. 9812715. The |
| notification was made because approximately one (1) quart of transmission |
| fluid (oil) was spilt onto the ground and was washed by existing weather |
| into the storm drain system which discharges into the plant cooling water |
| discharge canal. Plant systems were reviewed and there were no plant events |
| or occurrences that appear to be causally related. The water in the |
| discharge canal is river water that has been used for cooling plant |
| equipment during plant operation. The discharge canal has oil containment |
| barriers that are designed to contain the majority of oil discharges. |
| Additional action was taken to install temporary absorbent oil collection |
| booms in the discharge canal. Plant personnel initiated cleanup which is |
| continuing at this time. |
| |
| "This report is being made in accordance with 10 CFR 50.72(b)(2)(vi), for |
| any event related to the protection of the environment for which a |
| notification to another government agency (i.e., NYDEC) has been or will be |
| made." |
| |
| The licensee will inform the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35273 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ABB COMBUSTION ENGINEERING |NOTIFICATION DATE: 01/15/1999|
|LICENSEE: ABB COMBUSTION ENGINEERING |NOTIFICATION TIME: 16:37[EST]|
| CITY: WINDSOR REGION: 1 |EVENT DATE: 01/15/1999|
| COUNTY: STATE: CT |EVENT TIME: 16:37[EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 01/15/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BLAIR SPITZBERG R4 |
| |VERN HODGE NRR |
+------------------------------------------------+ |
| NRC NOTIFIED BY: VIRGIL PAGGEN | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PART 21 NOTIFICATION RELATED TO THE XL-S96 CPR CORRELATION FOR SVEA-96 |
| FUEL |
| |
| "The purpose of this letter is to notify the Nuclear Regulatory Commission |
| of a defect as defined in 10 CFR 21, 'Reporting of Defects and |
| Noncompliance.' The defect concerns the XL-S96 Critical Power Ratio (CPR) |
| correlation for ABB SVEA-96 fuel assemblies for Boiling Water Reactors |
| (BWRs). Specifically, the defect concerns the XL-S96 CPR correlation, which |
| is based solely on a cosine axial power shape. The defect could lead to |
| non-conservative Operating Limit MCPRs and monitored CPRs for top-peaked |
| axial power shapes. |
| |
| "The Enclosure summarizes the evaluation performed by ABB Combustion |
| Engineering (ABB-CE). If you have any questions, please feel free to contact |
| me [Ian C. Rickard] or Mr. Virgil Paggen of my staff." |
| |
| This event effects WNP-2 current operating cycle (Cycle 14). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35274 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: STATE OF KANSAS |NOTIFICATION DATE: 01/15/1999|
|LICENSEE: ASH GROVE CEMENT COMPANY. |NOTIFICATION TIME: 17:49[EST]|
| CITY: OVERLAND PARK REGION: 4 |EVENT DATE: 01/12/1999|
| COUNTY: STATE: KS |EVENT TIME: 15:10[CST]|
|LICENSE#: 22-B123-01 AGREEMENT: Y |LAST UPDATE DATE: 01/15/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BLAIR SPITZBERG R4 |
| |JOHN SURMEIER, EO NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TOM CONLEY | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STATE OF KANSAS NOTIFIED OF LEAKING GAS CHROMATOGRAPH SOURCE |
| |
| ON 1/12/99, THE KANSAS DEPARTMENT OF HEALTH AND ENVIRONMENT WAS NOTIFIED BY |
| A REPRESENTATIVE OF THE ASH GROVE CEMENT COMPANY LOCATED IN OVERLAND PARK, |
| KANSAS, THAT THEIR PERKIN ELMER GAS CHROMATOGRAPH MODEL # N610-0133 HAD |
| FAILED ITS ROUTINE LEAK TEST. THE TEST WHICH IS PERFORMED EVERY SIX MONTHS |
| REVEALED THAT 0.008 �Ci OF THE 15 mCi NICKEL-63 SOURCE HAD LEAKED (0.005 �Ci |
| IS THE ALLOWABLE LEAKAGE). THE INSTRUMENT WILL BE RETURNED TO THE |
| MANUFACTURER FOR SERVICE. THERE IS NO RISK SIGNIFICANCE ASSOCIATED WITH |
| THIS EVENT NOR WAS THERE ANY PERSONNEL DOSE OR CONTAMINATION INVOLVED. |
| KANSAS WILL CONTINUE ITS EVALUATION. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35275 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/15/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:08[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/15/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:10[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/18/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |JIM GAVULA R3 |
| DOCKET: 0707002 |JOHN SURMEIER NMSS |
+------------------------------------------------+FRANK CONGEL IRO |
| NRC NOTIFIED BY: RICHARD LARSON | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 4-HOUR NRC 91-01 BULLETIN NOTIFICATION INVOLVING ABANDONED EQUIPMENT IN THE |
| X-326 PROCESS BUILDING |
| |
| ON JANUARY 15, 1999, AT 1410 EST IT WAS DISCOVERED THAT THE X-326 PROCESS |
| BUILDING NUCLEAR CRITICALITY APPROVALS (NCSAs) DO NOT DESCRIBE THE |
| OPERATION/CONTROLS FOR THE FOLLOWING ABANDONED IN PLACE EQUIPMENT: PRODUCT |
| PURIFICATION DISTILLATION TOWER, OLD EVACUATION JETS, OLD SO2 REACTOR, OLD |
| PW BOOSTER CONNECTED TO CELL 25-7-15, AND [AN] OLD FREON DEGRADER. |
| |
| "THIS IS REPORTABLE DUE TO NOT HAVING ANY NCSA IN PLACE FOR THIS ABANDONED |
| EQUIPMENT. |
| |
| "THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT." |
| |
| A PRIOR NRC NOTIFICATION (EVENT #33627) WAS MADE WHICH IDENTIFIED LEGACY |
| EQUIPMENT IN THE X-326 PROCESS BUILDING, HOWEVER, THE ABOVE EQUIPMENT WAS |
| INADVERTENTLY OMITTED. THE EQUIPMENT IS IN GEOMETRICALLY FAVORABLE |
| CONDITIONS AND CONTAINS URANIUM BELOW THE SAFE MASS LIMIT. THIS CONDITION |
| WAS DISCOVERED IN A REVIEW OF COMPLETED NCSAs. |
| |
| THE LICENSEE WILL INFORM THE DOE SITE REPRESENTATIVE AND HAS INFORMED THE |
| NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE AT 1955 ON 1/18/99, BY LARSON, TAKEN BY WEAVER * * * |
| |
| "THIS IS REPORTABLE DUE TO NOT HAVING ANY NCSA IN PLACE FOR THIS ABANDON |
| EQUIPMENT. |
| |
| UPDATE: DUE TO THE PROBLEMS CONCERNING ABANDON EQUIPMENT IN THE X-326 |
| BUILDING NOT COVERED BY NUCLEAR CRITICALITY SAFETY APPROVALS (NCSAs), A |
| SEARCH PERFORMED IN THE X-705 & X-700 REVEALED ABANDON EQUIPMENT THAT MAY |
| NEED NCSAs. THE PLANT IS FOLLOWING IT'S PROCEDURE FOR ANOMALOUS NCSA |
| CONDITIONS AND FURTHER EVALUATIONS ARE IN PROGRESS TO DETERMINE IF THIS |
| ABANDON EQUIPMENT MEETS THE FISSILE MATERIAL LIMITS. THE FISSILE MATERIAL |
| LIMIT OF 15 GRAMS U235 BY PLANT PROCEDURES REQUIRES NCSAs." |
| |
| THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. |
| |
| The licensee informed the NRC resident inspector. The Operations Officer |
| notified the RDO (Gavula); EO (Surmeier); IRD (Congel). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35276 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 01/17/1999|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 10:21[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/17/1999|
+------------------------------------------------+EVENT TIME: 09:45[EST]|
| NRC NOTIFIED BY: MAY |LAST UPDATE DATE: 01/17/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GENE KELLY R1 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| LOST CAPABILITY FOR EMERGENCY NOTIFICATION THROUGH THE WEATHER RADIOS. |
| |
| THE LICENSEE WAS INFORMED THAT THE AMES HILL TRANSMITTER IS OUT OF SERVICE. |
| THIS FAILURE DEGRADES THE LICENSEE'S CAPABILITY FOR MAKING NOTIFICATIONS TO |
| THE PUBLIC THROUGH WEATHER RADIOS DURING AN EMERGENCY. TECHNICIANS ARE ON |
| THE WAY TO MAKE REPAIRS TO THE TRANSMITTER. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
| |
| * * * UPDATE 1310 EST ON 1/17/99 FROM MAY TO S. SANDIN * * * |
| |
| THE AMES HILL TRANSMITTER WAS RESTORED AS OF 1310 EST. NOTIFIED |
| R1DO(KELLY). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35277 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 01/18/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 09:26[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 01/18/1999|
+------------------------------------------------+EVENT TIME: 04:41[CST]|
| NRC NOTIFIED BY: FUNKHOUSER |LAST UPDATE DATE: 01/18/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM GAVULA R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE REACTOR WAS MANUALLY SCRAMMED WHILE IN COLD SHUTDOWN. |
| |
| WHILE PERFORMING CONTROL ROD VENTING WITH THE 24-17 ROD IN POSITION 48, THE |
| TRANSPONDER CARD IN THE ROD CONTROL & INSTRUMENT SYSTEM (RC&IS) FAILED. |
| THE ROD BECAME STUCK IN THIS POSITION, DUE TO THE RC&IS CARD FAILURE, AND |
| THE REACTOR WAS MANUALLY SCRAMMED. THE 24-17 ROD, THE ONLY ONE IN THE OUT |
| POSITION DURING ROD VENTING, WAS FULLY INSERTED AFTER THE SCRAM. THE CAUSE |
| OF THE RC&IS COMPONENT FAILURE IS UNKNOWN AND BEING INVESTIGATED. |
| |
| THE RESIDENT INSPECTOR WILL BE NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35278 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 01/18/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 12:56[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/15/1999|
+------------------------------------------------+EVENT TIME: 13:19[EST]|
| NRC NOTIFIED BY: ZAREMBA |LAST UPDATE DATE: 01/18/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GENE KELLY R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| BOTH VACUUM BREAKER PRESSURE SWITCHES FAIL QUARTERLY SURVEILLANCE |
| |
| "During an instrument Functional Test, on January 15, 1999, the trip point |
| settings for redundant pressure switches which actuate the Pressure |
| Suppression Chamber Reactor Building Vacuum Breakers were found to exceed |
| the value required by Tech Specs. |
| |
| "This condition was initially evaluated for reportability under 10 CFR 50.72 |
| on January 15, 1999 at approximately 1530 and determined to not be |
| reportable. Subsequent review has conservatively determined that this |
| condition is reportable under 10 CFR 50.72(b)(2)(iii). |
| |
| "Under certain accident conditions, this condition could have resulted in |
| higher differential pressure |
| (vacuum) between the Pressure Suppression Chamber and Reactor Building than |
| specified by Technical |
| Specifications and therefore, if assumed design margin is not credited, |
| could have challenged primary |
| containment integrity. |
| |
| "This condition was corrected immediately upon identification." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35279 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 01/18/1999|
| UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 14:46[EST]|
| RXTYPE: [1] W-2-LP |EVENT DATE: 12/29/1998|
+------------------------------------------------+EVENT TIME: 16:31[CST]|
| NRC NOTIFIED BY: GARY HARRINGTON |LAST UPDATE DATE: 01/18/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM GAVULA R3 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 95 Power Operation |95 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| EMERGENCY SIRENS INOPERABLE |
| |
| "Kewaunee was notified that the radio repeater used to set off the Kewaunee |
| County Sirens was out of service from an unknown time on 12/26/98 until |
| mid-day 12/28/98 (Saturday thru Monday). The failed repeater resulted in |
| greater than 50% of the Kewaunee area Emergency Notification Sirens being |
| out of service." |
| |
| Initially this event was determined not reportable due to the system being |
| returned to service before the plant was notified. However, subsequent |
| licensee discussions with a Region III Emergency Plan Inspector revealed the |
| condition should have been reported within 1 hour of Kewaunee being |
| notified. |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35280 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 01/18/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 21:46[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/18/1999|
+------------------------------------------------+EVENT TIME: 20:17[CST]|
| NRC NOTIFIED BY: CARL MOORE |LAST UPDATE DATE: 01/19/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |JIM GAVULA R3 |
|10 CFR SECTION: |BRUCE BOGER NRR |
|AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |FRANK CONGEL IRD |
| |SULLIVAN FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNUSUAL EVENT - LOSS OF APPROXIMATELY 50% OF CONTROL ROOM ANNUNCIATORS |
| |
| "Loss of redundant Annunciator Power Supplies has rendered a substantial |
| number of safety related annunciators inoperable. This required a GSEP |
| notification - Unusual Event, (MU-6 - Loss of Annunciators for >= 15 |
| minutes). Backup indications are available and increased main control board |
| monitoring has been implemented." |
| |
| The licensee has called in additional personnel to help with the increased |
| monitoring. Troubleshooting on the power supplies is in progress. The NRC |
| resident inspector has been notified. |
| |
| |
| *** UPDATE ON 01/19/99 @ 0539 BY RAUSH TO GOULD *** |
| |
| THE PLANT TERMINATED THE NOUE AT 0407 WHEN TESTING VERIFIED THE SYSTEMS WERE |
| FULLY OPERATIONAL. THE CAUSE OF THE POWER SUPPLY FAILURE WAS DUE TO A |
| GROUND WHICH HAS BEEN REPAIRED. BOTH BACKUP AND MAIN POWER SUPPLY HAVE |
| BEEN RETURNED TO SERVICE. |
| |
| THE NRC RESIDENT INSPECTOR AND THE STATE WAS NOTIFIED. |
| |
| THE REG 3 RDO(GAVULA) AND THE EO( BOGER )WERE NOTIFIED ALONG WITH FEMA |
| (WRIGHT). |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021