U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/10/95 - 10/11/95 ** EVENT NUMBERS ** 29436 29437 29438 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29436 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 10/10/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 12:01 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 10/10/95 | +------------------------------------------------+EVENT TIME: 11:35[EDT]| |NRC NOTIFIED BY: STEVE FULLER |LAST UPDATE DATE: 10/10/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PLANT SHUT DOWN PER TECH SPEC LCO 3.0.A DUE TO THE DISCOVERY OF A MISSED | | SURVEILLANCE ON SCRAM DISCHARGE INSTRUMENT VOLUME ISOLATION VALVES. THE | | VALVES WERE TESTED SATISFACTORILY AS OF 11:55 EDT ON 10/10/95. REACTOR | | POWER WAS NOT REDUCED, AND THE LCO WAS EXITED AT 11:55 EDT. THE TESTING | | WAS COMPLETED ELEVEN DAYS AFTER THE DUE DATE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29437 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 10/10/95 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 20:15 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/10/95 | +------------------------------------------------+EVENT TIME: 17:00[PDT]| |NRC NOTIFIED BY: JOY SKAGGS |LAST UPDATE DATE: 10/10/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS 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 N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN INCORRECT HEAT EXCHANGER FOULING FACTOR USED IN HEAT TRANSFER | | CALCULATIONS COULD CAUSE A HEAT OVERLOAD OF THE COMPONENT COOLING WATER | | SYSTEM. THIS OVERLOAD COULD INVALIDATE THE LICENSEE'S EXISTING | | ENVIRONMENTAL QUALIFICATION ASSUMPTIONS. | | | | GENERIC LETTER 89-13 EXEMPTED CLOSED COOLING WATER SYSTEMS WITH GOOD | | CHEMISTRY CONTROLS FROM PERFORMANCE TESTING. THE DIABLO CANYON COMPONENT | | COOLING WATER (CCW) SYSTEM IS A CLOSED COOLING SYSTEM WHICH HAS MAINTAINED | | GOOD CHEMISTRY CONTROL WITH ADDED INHIBITORS. | | | | THE INHIBITOR BEING USED WAS RECENTLY CHANGED BY MOVING TO A MORE | | ENVIRONMENTALLY FRIENDLY INHIBITOR. SINCE THIS CHANGE, THE SYSTEM HAS BEEN | | EXPERIENCING SOME MICROBE GROWTH WHICH RAISED CONCERNS FOR POTENTIAL | | DE-GRADING OF HEAT TRANSFER CAPABILITIES. PG&E HAS CONCLUDED A NUMBER OF | | TESTS AND INSPECTIONS TO BETTER UNDERSTAND THIS EFFECT. PG&E FURTHER | | ELECTED TO SPECIFICALLY TEST THE RESIDUAL HEAT REMOVAL (RHR) HEAT EXCHANGER | | DURING THE CURRENT 1R7 OUTAGE. | | | | THE PRELIMINARY TEST RESULTS SHOWED THAT THE FOULING WAS SIGNIFICANTLY | | "LESS", RATHER THAN "GREATER THAN" THE DESIGN VALUE ASSUMED IN THE ACCIDENT | | ANALYSIS. THE RESULT IS THAT INCREASED HEAT TRANSFER CAUSES INCREASED CCW | | TEMPERATURE DURING A DESIGN BASIS ACCIDENT. PRELIMINARY CALCULATIONS | | INDICATE TEMPERATURE EXCURSIONS BEYOND THOSE REPORTED IN THE DIABLO CANYON | | FSAR AND SSER 16. THE FSAR AND SSER 16 CONTAIN A 132 DEGREE F UPPER LIMIT | | RETURNING TO UNDER 120 DEGREES F WITHIN 20 MINUTES IN ORDER TO ASSURE | | AVAILABILITY OF VITAL PUMPS BASED UPON ORIGINAL GUIDANCE FROM THE | | SUPPLIERS. SUBSEQUENT EVALUATIONS BY PG&E, WESTINGHOUSE, AND EQUIPMENT | | SUPPLIERS INDICATE THAT ACTUAL EQUIPMENT COMPONENT CAPABILITIES MAY BE | | SIGNIFICANTLY GREATER THAN THAT REPORTED DURING THE LICENSING OF DIABLO | | CANYON. | | | | IN ADDITION, WESTINGHOUSE HAS PERFORMED A REVISED CONTAINMENT AND HEAT | | TRANSFER ANALYSIS USING NRC APPROVED CONTAINMENT ANALYSIS CODES. THIS | | ANALYSIS AND THE UPDATED EVALUATION OF COMPONENT CAPABILITY DURING ELEVATED | | CCW TEMPERATURES INDICATE THAT EQUIPMENT OPERABILITY IS NOT AFFECTED. PG&E | | IS DISCUSSING THE CCW TEMPERATURE LIMITS IN SSER 16 WITH NRR TO DETERMINE | | IF NRC REVIEW AND APPROVAL IS REQUIRED PRIOR TO CHANGING THIS LIMIT. | | PENDING COMPLETION OF THESE DISCUSSIONS, PG&E IS CONSERVATIVELY REPORTING | | THIS CONDITION AS BEING OUTSIDE ITS CURRENT DESIGN BASIS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29438 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 10/10/95 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 22:07 [ET]| |RX TYPE: [3] CE |EVENT DATE: 10/10/95 | +------------------------------------------------+EVENT TIME: 20:10[CDT]| |NRC NOTIFIED BY: VICTOR COLLINS |LAST UPDATE DATE: 10/10/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ONE-HOUR SECURITY REPORT | | | | A CONTRACT CUSTODIAL WORKER LIED ON HIS APPLICATION. BASED ON INITIAL | | REVIEW, HE WAS GIVEN UNESCORTED ACCESS. HIS ACCESS WAS TERMINATED WHEN THE | | FALSIFICATION WAS DISCOVERED. THE INDIVIDUAL HAD UNESCORTED ACCESS FOR | | APPROXIMATELY THREE WEEKS. PLANT SECURITY IS CHECKING HIS MOVEMENTS WITHIN | | THE SITE DURING THAT TIME. THE INDIVIDUAL HAD A PENDING FELONY ARREST HE | | DID NOT DISCLOSE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+