U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/04/95 - 12/05/95 ** EVENT NUMBERS ** 29666 29667 29668 29669 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29666 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 12/04/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 13:39 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/04/95 | +------------------------------------------------+EVENT TIME: 11:02[EST]| |NRC NOTIFIED BY: ART BREADY |LAST UPDATE DATE: 12/04/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE "A" SAFETY AUXILIARY COOLING SYSTEM (SACS) DECLARED INOPERABLE | | | | THE "A" SACS WAS DECLARED INOPERABLE BECAUSE THE TEMPERATURE OF THE SYSTEM | | IS BELOW THE 65øF MINIMUM REQUIRED IN THE FSAR DESIGN BASES. THE "A" SACS | | IS STILL CONSIDERED AVAILABLE. THE "B" SACS SYSTEMS IS TAGGED OUT AND | | DRAINED FOR MAINTENANCE. | | | | ALL SAFETY RELATED EQUIPMENT SUPPORTED BY THE SACS SYSTEM IS CURRENTLY | | INOPERABLE. THIS INCLUDES THE DIESELS AND THE EMERGENCY CORE COOLING | | SYSTEMS. TECH SPECS REQUIRE THAT CORE ALTERATIONS BE SUSPENDED. NONE WERE | | IN PROGRESS AT THE TIME OF THIS DISCOVERY, ALTHOUGH THIS IS A REFUELING | | OUTAGE, AND SOME FUEL HAS BEEN MOVED. | | | | THE PLANT IS STABLE AND ALL SAFETY SYSTEMS ASSOCIATED WITH THE "A" SACS | | SYSTEM ARE AVAILABLE. | | | | THE LICENSEE MAY HAVE UNKNOWINGLY ENCOUNTERED THIS CONDITION PRIOR TO THIS | | EVENT. AN ENGINEERING EVALUATION IS IN PROGRESS TO DETERMINE CORRECTIVE | | ACTION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29667 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 12/04/95 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 15:43 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/04/95 | +------------------------------------------------+EVENT TIME: 14:00[CST]| |NRC NOTIFIED BY: WALTER CADE |LAST UPDATE DATE: 12/04/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CRD SYSTEM FLOW NOT PROPERLY ACCOUNTED FOR IN THE CALORIMETRIC CALCULATION | | | | THIS REPORT WAS MADE AS A 24 HOUR REPORT IAW LICENSE CONDITION 2.C.1. CRD | | FLOW IS NONCONSERVATIVELY ACCOUNTED FOR IN THE CALORIMETRIC BECAUSE SOME OF | | THE FLOW IS DIVERTED FROM THE CRD SYSTEM PRIOR TO REACHING THE FLOW | | INSTRUMENTATION IN THE SYSTEM. THIS CAUSES CRD FLOW TO INDICATE LOWER THAN | | ACTUAL AS RELATED TO THE CALORIMETRIC CALCULATION. THE NET RESULT OF THIS | | ERROR IS THAT THERMAL POWER IS UNDERESTIMATED BY AS MUCH AS 0.8 MWt. THE | | PLANT'S LICENSED THERMAL POWER LIMIT IS 3833 MWt. THE THERMAL POWER LIMIT | | WAS PROBABLY SLIGHTLY EXCEEDED IN THE PAST. | | | | THE LICENSEE IS LIMITING POWER TO 3832 MWt UNTIL APPROPRIATE CHANGES CAN BE | | MADE TO THE CALORIMETRIC CALCULATION. THE LICENSEE INVESTIGATED THIS | | PROBLEM BECAUSE OF A SIMILAR DISCOVERY AT NINE MILE POINT, REPORTED IN | | EVENT #29603. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29668 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 12/04/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:25 [ET]| |RX TYPE: [1] CE |EVENT DATE: 12/04/95 | +------------------------------------------------+EVENT TIME: 15:40[CST]| |NRC NOTIFIED BY: BILL WEBER |LAST UPDATE DATE: 12/04/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE QUANTITY OF TRI-SODIUM PHOSPHATE (TSP) MAINTAINED IN THE CONTAINMENT | | SUMP HAS AT TIMES BEEN INADEQUATE | | | | THE FORT CALHOUN STATION, UNIT 1 IS REQUIRED TO MAINTAIN THE QUANTITY OF | | TSP DODECAHYDRATE IN THE CONTAINMENT SUMP TO NEUTRALIZE THE BORIC ACID FROM | | THE CONTAINMENT SPRAYS AND SAFETY INJECTION SYSTEMS AFTER A LOCA. THE | | NEUTRALIZATION IS TO PREVENT CHLORIDE INDUCED STRESS CORROSION CRACKING | | (SCC) IN CERTAIN MATERIALS (STAINLESS STEEL). A CALCULATION, UTILIZING A | | CONSERVATIVE METHODOLOGY, TO ASSURE A NEUTRAL SOLUTION WAS OBTAINED FROM | | THE NUCLEAR STEAM SYSTEM SUPPLY VENDOR ON NOVEMBER 28, 1995. THE | | SIGNIFICANCE OF THESE UPDATED CALCULATIONS CONCLUDED THAT THE QUANTITY OF | | TSP AT TIMES HAS FAILED TO BE SUFFICIENT TO NEUTRALIZE THE SUMP WATER TO A | | PH GREATER THAN 7.0 WHICH IS THE LICENSING BASIS FOR T.S. 3.6.2.(d). | | | | FORT CALHOUN STATION CURRENTLY LACKS CONTROLS ON THE ALLOWABLE BORON | | CONCENTRATION IN THE BORIC ACID STORAGE TANK, SAFETY INJECTION REFUELING | | WATER TANK, AND SAFETY INJECTION TANKS TO PREVENT EXCEEDING A POST ACCIDENT | | PH OF 7.0. | | | | TO ASSURE A POST ACCIDENT PH REMAINS GREATER THAN 7.0, INCREASES IN THE | | BORON CONCENTRATION IN THE BORIC ACID STORAGE TANK, SAFETY INJECTION | | REFUELING WATER TANK, AND SAFETY INJECTION TANKS WILL BE PROHIBITED BY | | NOTES IN THE SHIFT SUPERVISOR'S LOG AND THE CONTROL ROOM LOG. LONG TERM | | ACTIONS WILL INCLUDE A PROCEDURE CHANGE TO LIMIT BORON CONCENTRATIONS WHEN | | QUALITY ASSURED CALCULATIONS ARE COMPLETED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29669 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 12/05/95 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 01:05 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 12/05/95 | +------------------------------------------------+EVENT TIME: 00:25[EST]| |NRC NOTIFIED BY: JIM READY |LAST UPDATE DATE: 12/05/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED THE UNITED STATES COAST GUARD AND THE NEW YORK DEPARTMENT | | OF ENVIRONMENTAL CONSERVATION THAT THEY SPILLED ONE QUART OF OIL INTO THE | | HUDSON RIVER. | | | | APPROXIMATELY ONE QUART OF # 6 FUEL OIL WAS SPILLED TO THE HUDSON RIVER AS | | A RESULT OF A HOSE FAILURE DURING A FUEL OIL LINE HYDROSTATIC TEST. AN OIL | | BOOM WAS IN PLACED PRIOR TO THE SPILL, HOWEVER SOME OIL ESCAPED FROM THE | | BOOMED AREA INTO THE HUDSON RIVER. LICENSEE NOTIFIED UNITED STATES COAST | | GUARD NATIONAL RESPONSE CENTER, NEW YORK DEPARTMENT OF ENVIRONMENTAL | | CONSERVATION, AND THE WESTCHESTER COUNTY DEPARTMENT OF HEALTH OF THE OIL | | SPILL. | | | | RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT. | +------------------------------------------------------------------------------+