U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/21/97 - 01/22/97 ** EVENT NUMBERS ** 31581 31626 31627 31628 31629 31630 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31581 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BASF |NOTIFICATION DATE: 01/13/97 | | CITY: REGION: 2 |NOTIFICATION TIME: 14:37 [ET]| | COUNTY: STATE: NC |EVENT DATE: 01/13/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 13:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/21/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHRISTENSEN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: HIGHTOWER | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT | | | | THE NC STATE DIVISION OF RADIATION PROTECTION NOTIFIED THE OPERATIONS | | CENTER THAT BASF, A NORTH CAROLINA LICENSEE, DISCOVERED THE LOSS OF TWO | | 8mCi Ni-63 SOURCES. THE LICENSEE BELIEVES THAT THE SOURCES WERE REMOVED | | FROM SOME EQUIPMENT THAT BASF DONATED TO WAKE TECHNICAL COLLEGE IN DECEMBER | | OF 1996. | | | | * * * UPDATE 0915EST 1/21/97 FROM WOODRUFF (REGION 2) TO S.SANDIN * * * | | | | REGION 2 WAS INFORMED THAT THE LICENSEE HAS RECOVERED THE LOST SOURCES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31626 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NJ DEP |NOTIFICATION DATE: 01/21/97 | | CITY: EWING REGION: 1 |NOTIFICATION TIME: 12:36 [ET]| | COUNTY: STATE: NJ |EVENT DATE: 01/17/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 12:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/21/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM MOSLAK RDO | | |Dr COOL (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: STEVE BOYKEWICK | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 30 - 50ęCi OF CS-137 FOUND IN A SCRAP YARD. | | | | THE NEW JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION (RADIATION PROTECTION | | PROGRAMS) LOCATED AT 25 ARCTIC PARKWAY, TRENTON, NJ. RELAYED THE FOLLOWING | | INFORMATION: | | | | THE NEW JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION (RADIATION PROTECTION | | PROGRAMS) WAS NOTIFIED BY THE MICHIGAN RADIOLOGICAL SECTION THAT A | | CONTAMINATED WASTE SHIPMENT FROM NIMCO SHREDDING LOCATED IN NEW JERSEY HAD | | BEEN SHIPPED TO HURON VALLEY STEEL, LOCATED IN BELLEVILLE, MICHIGAN ON | | 01/13/97. THE CONTAMINATED SHIPMENT WAS RETURNED TO NIMCO ON 01/14/97. | | NIMCO WAS ABLE TO ISOLATE THE SOURCE OF RADIOLOGICAL CONTAMINATION. A SMALL | | METALLIC OBJECT APPROXIMATELY 0.125" IN DIA BY 0.1875" LONG WAS FOUND. | | NIMCO HAS SECURED THE SOURCE IN A STURDY METAL CONTAINER AND WRAPPED THE | | CONTAINER WITH SHEETS OF LEAD. | | THE NEW JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION WENT OUT TO NIMCO ON | | 01/17/97 WITH A GAMMA SPEC SYSTEM AND IDENTIFIED THE RADIOACTIVE OBJECT AS | | 30 - 50ęCi OF CS-137. NOBODY KNOWS WHERE THIS OBJECT CAME FROM. THE NEW | | JERSEY DEPARTMENT OF ENVIRONMENTAL PROTECTION NOTIFIED NRC REGION 1 OFFICE | | OF THIS EVENT. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31627 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 01/21/97 | |UNIT: [ ] [2] [3] STATE: AL |NOTIFICATION TIME: 14:23 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 01/21/97 | +------------------------------------------------+EVENT TIME: 10:00[CST]| |NRC NOTIFIED BY: TERRY KNUETTEL |LAST UPDATE DATE: 01/21/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 87 POWER OPERATION | 87 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A TVA MANAGER TESTED POSITIVE FOR ALCOHOL. HE WAS RELIEVED OF DUTY, HIS | | CLEARANCE WAS SUSPENDED AND HE WAS ESCORTED OFF SITE. AN INVESTIGATION IS | | ON-GOING. THE LICENSEE INFORMED REGION 2 (THOMPSON) AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31628 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 01/21/97 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 15:37 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 01/21/97 | +------------------------------------------------+EVENT TIME: 09:30[EST]| |NRC NOTIFIED BY: ARTHUR CUMMINGS |LAST UPDATE DATE: 01/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CONTRACT SUPERVISOR TESTED POSITIVE FOR DRUGS DURING A RANDOM DRUG TEST. | | | | AT 0930 THE FLORIDA POWER AND LIGHT MEDICAL REVIEW OFFICER NOTIFIED THE | | LICENSEE THAT A BADGED CONTRACTOR SUPERVISOR TESTED POSITIVE FOR MARIJUANA. | | HIS UNESCORTED ACCESS WAS REVOKED. A REVIEW OF THE PERSONS WORK WILL BE | | CONDUCTED TO CHECK HIS QUALITY OF WORK. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31629 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 01/21/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/21/97 | +------------------------------------------------+EVENT TIME: 15:00[CST]| |NRC NOTIFIED BY: M STRACKA |LAST UPDATE DATE: 01/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OPERABILITY STRESS LIMITS FOR PIPING SYSTEMS EVALUATED PER NRC GENERIC | | LETTER 91-18. | | | | THE FOLLOWING TEXT WAS TAKEN FROM A FACSIMILE SENT BY THE LICENSEE: | | | | "PRELIMINARY RESULTS (COMED CALCULATIONS 22S-1-004M-206/UNIT 1 AND | | 22S-2-004M-2C/UNIT 2) INDICATE THAT PIPE STRESSES AND PIPE SUPPORT LOADS | | ARE WITHIN OPERABILITY STRESS LIMITS. THESE PRELIMINARY RESULTS ARE BASED | | ON A COMPUTER REANALYSIS OF THE PRESSURIZER RELIEF PIPING USING THE REVISED | | (HIGHER) DESIGN TEMPERATURES AND PRESSURES, INCLUDING AN ASSUMED | | CONSERVATIVE PORV LIFT TRANSIENT. THESE CALCULATIONS ARE NOT FINAL AND THE | | COMPUTATION OF SUPPORT LOADS/STRESS NOZZLE LOADS/STRESS, AND PIPE STRESSES | | IS NOT COMPLETE. OPERABILITY STRESS LIMITS FOR PIPING SYSTEMS DEMONSTRATE | | THAT THE PIPING IS CAPABLE OF PERFORMING THE FUNCTIONAL REQUIREMENT OF | | PASSING FLOW AND MAINTAINING PRESSURE BOUNDARY. USING OPERABILITY STRESS | | LIMITS TO DEMONSTRATE PIPING SYSTEM OPERABILITY IS DISCUSSED IN NRC GENERIC | | LETTER 91-18." | | | | "THE PRELIMINARY RESULTS FOR THIS ANALYSIS INDICATE THAT PIPE STRESS DESIGN | | LIMITS ARE MET FOR PRESSURE, GRAVITY, AND THERMAL EXPANSION STRESSES. | | DESIGN LIMITS FOR PIPE STRESS ARE NOT MET FOR LOAD COMBINATIONS INVOLVING | | DYNAMIC LOADS. FOR THESE LOAD CASES, THE MAXIMUM STRESSES ARE LESS THAN THE | | ASME CODE FAULTED ALLOWABLE OF 2.4S(sub h). THEREFORE, PIPE STRESSES ARE | | WELL WITHIN THE OPERABILITY STRESS LIMIT OF 2S(sub y). | | | | "A PRELIMINARY REVIEW OF SUPPORT LOAD INCREASES INDICATES THAT THE REVISED | | LOADS ARE LESS THAN THE FAULTED ALLOWABLE FOR THE STANDARD PIPE SUPPORT | | COMPONENTS. PRELIMINARY CALCULATIONS EVALUATING THE MOUNTING PLATES, ANCHOR | | BOLTS AND AUXILIARY STEEL INDICATE THAT THE STRESSES ARE WITHIN OPERABILITY | | LIMITS. | | | | "THE PRESSURIZER NOZZLES ARE THE SAME FOR THE FOUR RELIEF/SAFETY LINES. THE | | PRELIMINARY NOZZLE LOAD INCREASES ON ANY ONE NOZZLE ARE LESS THAN THAT | | PREVIOUSLY QUALIFIED FOR THE GOVERNING NOZZLE LOAD. THE PRT NOZZLE LOAD | | INCREASES WERE EVALUATED AND ARE ACCEPTABLE. THEREFORE, THE NOZZLE LOAD | | INCREASES ARE CONSIDERED ACCEPTABLE." | | | | THE ONE HOUR OUTSIDE DESIGN BASIS EVENT CLASSIFICATION IS FOR UNIT 1 WHICH | | IS AT POWER. THE FOUR HOUR DEGRADED WHILE SHUTDOWN EVENT CLASSIFICATION IS | | FOR UNIT 2 WHICH IS IN A COLD SHUTDOWN CONDITION. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31630 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 01/21/97 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 17:39 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/21/97 | +------------------------------------------------+EVENT TIME: 17:10[EST]| |NRC NOTIFIED BY: TOM TYNAN |LAST UPDATE DATE: 01/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PORTIONS OF THE NUCLEAR SERVICE WATER SYSTEM AND SEVERAL CONTAINMENT | | PENETRATIONS HAVE BEEN DETERMINED TO BE OUTSIDE THEIR DESIGN BASIS. | | | | | | THE FOLLOWING TEXT WAS TAKEN FROM A FACSIMILE SENT BY THE LICENSEE: | | | | "DURING EVALUATION OF NRC GENERIC LETTER 96-06 "ASSURANCE OF EQUIPMENT | | OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN BASIS ACCIDENT | | CONDITIONS" PORTIONS OF THE NUCLEAR SERVICE COOLING WATER (NSCW) SYSTEM AND | | SEVERAL CONTAINMENT PENETRATIONS HAVE BEEN DETERMINED TO BE OUTSIDE OF | | THEIR DESIGN BASES. BASED ON POSTULATED DESIGN EVENTS DESCRIBED IN THIS | | LETTER DURING A LOSP ALONG WITH A MSLB/LOCA, IT HAS BEEN DETERMINED THAT | | THE VOGTLE'S NSCW SYSTEM IS SUSCEPTIBLE TO WATER HAMMERS. SOME OF THE | | PIPING SYSTEM, SUPPORTS AND EQUIPMENT ARE OUTSIDE THEIR DESIGN BASIS DURING | | THIS POSTULATED EVENT. | | | | "ADDITIONALLY, THE GENERIC LETTER ADDRESSED THE POSSIBILITY OF CONTAINMENT | | PENETRATION OVERPRESSURIZATION DURING A LOCA ENVIRONMENT INSIDE CONTAINMENT | | ONCE THE PENETRATION HAS BEEN ISOLATED. SEVERAL PENETRATIONS HAVE BEEN | | DETERMINED TO BE SUSCEPTIBLE TO THIS CONDITION AND THE RESULTING PIPE | | STRESS WOULD BE OUTSIDE THEIR ASME CODE ALLOWABLES FOLLOWING A DESIGN BASES | | ACCIDENT. | | | | "ALTHOUGH ENGINEERING ANALYSIS IS CONTINUING, IT IS CURRENTLY BELIEVED THAT | | ALL CONTAINMENT COOLERS AND PIPING, ALONG WITH, CONTAINMENT PENETRATIONS, | | WILL CONTINUE TO PERFORM THEIR REQUIRED SAFETY FUNCTIONS DURING THE ABOVE | | CONDITION. THIS IS BEING REPORTED IN ACCORDANCE WITH | | 10CFR50.72(b)(1)(ii)(B), AS BEING IN A CONDITION OUTSIDE THE DESIGN BASIS | | OF THE PLANT." | | | | THE NRC RESIDENT WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | +------------------------------------------------------------------------------+