U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/04/97 - 11/05/97 ** EVENT NUMBERS ** 33207 33208 33209 33210 33211 33212 +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33207 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/04/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 05:27 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/04/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 01:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/04/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MIKE JORDAN RDO | | DOCKET: 0707002 |MARGARET FEDERLINE EO | +------------------------------------------------+JOSEPH GIITTER IRD | |NRC NOTIFIED BY: STEVE MAY | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FOUR HOUR NRCB 91-01 REPORT INVOLVING LOSS OF TWO CRITICALITY CONTROL | | PARAMETERS | | | | "AT 0130 TUESDAY NOVEMBER 4, 1997, IT WAS DETERMINED THAT AN INCIDENT | | DISCOVERED IN THE X-333 AND X-330 PROCESS BUILDINGS CONSTITUTED A 4-HOUR | | REPORTABLE EVENT. THIS EVENT IS DUE TO CASCADE OPERATIONS PERSONNEL | | DISCOVERING 14 CELLS WITH DRAIN VALVES CLOSED ON THE RCW [RECIRCULATING | | COOLING WATER] CONDENSER. ONE CELL, 29-5-8, IS A PEH (PLANNED EXPEDITIOUS | | HANDLING) CELL. THE DRAIN VALVE ON 29-58-8 WAS OPENED AND THE RESIDUAL RCW | | DRAINED. THIS DISCOVERY CONSTITUTED A VIOLATION OF THE NUCLEAR CRITICALITY | | SAFETY APPROVAL (NCSA) NCSA-0333_015.A01 AND NCSA-0030_005.A01. THIS EVENT | | RESULTED IN A LOSS OF BOTH CONTROL A AND CONTROL B AS NOTED [IN] THIS | | REPORT. THESE CONTROLS WERE ESTABLISHED TO PREVENT THE INTRODUCTION OF RCW | | INTO THE URANIUM ENRICHMENT CASCADE. THERE WAS NO RELEASE OF HAZARDOUS | | MATERIALS OR RADIOLOGICAL CONTAMINATION ASSOCIATED WITH THIS EVENT. THIS | | EVENT IS BEING REPORTED PER NUCLEAR REGULATORY EVENT REPORTING PROCEDURE | | UE2-RA-RE1030, APPENDIX D, CRITERIA A, PARAGRAPH 4.b. | | | | SAFETY SIGNIFICANCE: RCW COULD ENTER THE R-114 COOLANT SYSTEM AND | | ULTIMATELY ALLOW MODERATOR TO ENTER THE UF6 SYSTEM. CONDENSER TUBE LEAKS | | AND R-114 COOLER TUBE LEAKS WOULD HAVE TO SIMULTANEOUS BE PRESENT FOR THIS | | FAILURE MODE TO OCCUR. | | | | POTENTIAL CRITICALITY PATHWAYS INVOLVED: THE RCW CONDENSER MUST REMAIN | | DRAINED TO PREVENT MODERATOR (RCW) FROM POSSIBLY ENTERING THE UF6 SYSTEM. | | | | CONTROLLED PARAMETERS: | | CONDITION A - PROTECTION FROM RCW INLEAKAGE INTO THE CASCADE SHALL BE | | ASSURED BY MAINTAINING THE COOLANT PRESSURE ABOVE BOTH THE UF6 AND RCW | | PRESSURES. | | CONDITION B - WHEN A CELL IS SHUTDOWN (MOTOR TURNED OFF) AND THE R-114 | | REMOVED, THE RCW SUPPLY TO THE AFFECTED CELL SHALL BE VALVED OFF, THE | | CONDENSER DRAINED, AND THE DRAIN VALVE LEFT OPEN. THE RCW SHALL REMAIN | | VALVED OFF UNTIL THE R-114 IS RETURNED TO THE SYSTEM. | | | | NUCLEAR CRITICALITY SAFETY CONTROLS: THIS EVENT INVOLVED THE LOSS OF | | CONTROL FOR BOTH CONTROL A & B ABOVE. | | | | CORRECTIVE ACTIONS: THE RCS DRAIN VALVES WILL BE OPENED, AND THE RESIDUAL | | RCW DRAINED FROM THE CONDENSER. ALL CELL TREATMENT ACTIVITIES HAVE BEEN | | PLACED ON HOLD PENDING NCSA REVIEW. ALL OTHER OFFLINE CELLS ARE BEING | | INSPECTED FOR CLOSED RCW CONDENSER DRAIN VALVES." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33208 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 11/04/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 13:54 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 11/04/97 | +------------------------------------------------+EVENT TIME: 13:00[EST]| |NRC NOTIFIED BY: MIKE JACOBS |LAST UPDATE DATE: 11/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEANNE HARRISON 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 +------------------------------------------------------------------------------+ | SEVERAL DESIGN ISSUES WHICH WERE NOT PREVIOUSLY REPORTED ARE IDENTIFIED IN | | NRC INSPECTION REPORT #97-05. | | | | FIVE "OUTSIDE THE DESIGN BASIS OF THE PLANT" ISSUES WERE IDENTIFIED DURING | | AN HISTORICAL REVIEW BY NRC INSPECTORS. THESE ISSUES INCLUDING DATE OF | | OCCURRENCE ARE AS FOLLOWS: | | | | 1. "(7/18/94) SERVICE WATER INLET TEMPERATURE (THE ULTIMATE HEAT SINK) | | EXCEEDED DESIGN LIMIT OF 65øF ON SEVERAL OCCASIONS DURING THE SUMMER MONTHS | | OF 1994. ON JULY 3, 1997 PNPS RECEIVED LICENSE AMENDMENT 173 WHICH CHANGED | | THE DESIGN LIMIT FOR SERVICE WASTER INLET TEMPERATURE TO 75øF." | | | | 2. "(1/26/96) ERROR WAS FOUND IN GE CONTAINMENT ANALYSIS. SPECIFICALLY, | | THE NEW DRYWELL TEMPERATURE PROFILES PROVIDED BY GE WERE NOT SIMILAR TO THE | | ANALYSIS OF RECORD (LESS CONSERVATIVE). THIS AFFECTED QUALIFICATION OF EQ | | EQUIPMENT INSIDE THE DRYWELL. THE EQUIPMENT IS NOW QUALIFIED AND THE FSAR | | HAS BEEN CHANGED TO INCORPORATE CORRECT TEMPERATURE PROFILE." | | | | 3. "(9/9/97) SWOPI INSPECTION TEAM FOUND THAT REACTOR BUILDING CLOSED | | COOLING WATER (RBCCW) FLOW TO NONESSENTIAL LOADS IS ASSUMED TO BE ISOLATED | | DURING ACCIDENT CONDITIONS. THERE WAS, HOWEVER, NO PROCEDURAL GUIDANCE TO | | ISOLATE THESE COMPONENTS DURING AN ACCIDENT. PLANT PROCEDURE HAS BEEN | | CHANGED TO ADDRESS CLOSURE OF THE RBCCW NONESSENTIAL BLOCKS." | | | | 4. "(5/30/97) PLANT OPERATING PROCEDURE DIRECTED AN RHR FLOW RATE WHICH IS | | NOT CONSISTENT WITH THE ACCIDENT ANALYSIS (ACCIDENT ANALYSIS USES 5100 GPM, | | PLANT PROCEDURE GAVE OPERATING RANGE OF 4800 TO 5100 GPM). WE HAVE AN | | ENGINEERING EVALUATION FOR OPERABILITY." | | | | 5. "(6/13/97) VENDOR MANUAL FOR THE EMERGENCY DIESEL GENERATORS | | ESTABLISHES A MAXIMUM DESIGN AMBIENT TEMPERATURE OF 88øF. DURING SUMMER | | MONTHS AT PILGRIM NUCLEAR POWER STATION AMBIENT TEMPERATURE EXCEEDED 88øF. | | TEMPERATURES AT THIS TIME ARE WELL BELOW 88øF." | | | | THESE ISSUES WILL BE DISCUSSED IN AN UPCOMING ENFORCEMENT CONFERENCE WITH | | THE NRC AS POTENTIAL VIOLATIONS. | | | | THE LICENSEE INFORMED STATE AUTHORITIES AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33209 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 11/04/97 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 14:18 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/04/97 | +------------------------------------------------+EVENT TIME: 13:22[EST]| |NRC NOTIFIED BY: PAGE KEMP |LAST UPDATE DATE: 11/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |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 OTHER FEDERAL AGENCY REGARDING SMALL LEAK IN | | CONCRETE SPILLWAY OF DAM. | | | | "THE FERC REGIONAL ENGINEER WAS NOTIFIED OF A SMALL LEAK IN THE CONCRETE | | SPILLWAY BELOW RADIAL GATE 1-SP-R6-18 AS REQUIRED BY VPAP-2802 6.3.2.i.2. | | THAT REPORT (REQUIRED BY VPAP-2802) TO ANOTHER FEDERAL AGENCY, OR TO A | | STATE, OR LOCAL GOVERNMENT AGENCY REQUIRES A FOUR HOUR NON-EMERGENCY REPORT | | TO THE NRC. | | | | "THIS LEAK IS AT A CONCRETE CONSTRUCTION JOINT ASSOCIATED WITH THE ORIGINAL | | SLUICE OPENING THAT EXISTED BEFORE THE RESERVOIR WAS FLOODED. THIS TYPE OF | | SMALL LEAK DOES NOT COMPROMISE THE STRUCTURAL INTEGRITY OF THE MAIN DAM. | | HOWEVER, THE ENGINEER RECOMMENDS MONITORING THE LEAK FOR ANY VISIBLE CHANGE | | IN FLOW VOLUME OR CHARACTERISTIC. REPAIR WILL BE CONSIDERED FOR INCLUSION | | INTO THE SUMMER 1998 SCHEDULED MAINTENANCE WORK AT THE DAM." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33210 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/04/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:25 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/03/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/04/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |MIKE JORDAN RDO | | DOCKET: 0707002 |DON COOL EO | +------------------------------------------------+RICHARD BARRETT IRD | |NRC NOTIFIED BY: ERIC SPAETH | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24 HOUR NRC BULLETIN 91-01 NOTIFICATION BASED ON LOSS OF ONE CRITICALITY | | CONTROL PARAMETER. | | | | "AT 1630 HOURS ON 11/3/97, IT WAS DISCOVERED THAT A NUCLEAR CRITICALITY | | SAFETY APPROVAL (NCSA) REQUIREMENT WAS NOT BEING MET IN THE X-710 LAB | | FACILITY. NCSA-0710-008 LISTS TWO (2) NUCLEAR CRITICALITY SAFETY CONTROLS | | FOR THE X-710, ROOM 114, ISOTOPIC STANDARDS PREP. ROOM. THE FIRST CONTROL | | REQUIRES ALL URANIUM BEARING MATERIALS MUST BE KEPT AT LEAST TWO (2) FEET | | FROM EACH OF THE STORAGE LOCATIONS, AND THE SECOND CONTROL REQUIRES THAT | | ARRAYS OF SMALL CONTAINERS, WHEN PLACED ON THE RAISED SHELVES ON THE NORTH | | AND EAST WALLS, SHALL BE RESTRICTED TO CONFIGURATIONS APPROXIMATING A | | 'SAFE' PIPE GEOMETRY BY PLACING CONTAINERS WITH A MAX. FILL HEIGHT OF 5 | | INCHES AND A MAX. DIAMETER OF 5 INCHES IN A SINGLE STRAIGHT LINE AND | | END-TO-END. THE FIRST CONTROL WAS VIOLATED WHEN IT WAS DISCOVERED THAT 2 | | SAMPLE CONTAINERS STORED ON THE EAST WALL RAISED SHELF WERE WITHIN 24 | | INCHES OF THE ARRAY OF 2S SAMPLE CYLINDERS STORED ON THE WORK BENCH BELOW. | | THE SECOND CONTROL WAS MAINTAINED THROUGHOUT THIS EVENT. THE LOSS OF ONE | | CONTROL (SPACING) MAKES THIS EVENT REPORTABLE TO THE NRC VIA A 24 HOUR | | EVENT NOTIFICATION PER NUCLEAR REGULATORY EVENT REPORTING PROCEDURE | | UE2-RA-RE130, APP. D, CRITERIA A, PARAGRAPH 4a. THERE WAS NO RELEASE OF | | HAZARDOUS MATERIALS OR RADIOLOGICAL CONTAMINATION EXPOSURE ASSOCIATED WITH | | THIS EVENT." | | | | THE FOLLOWING ADDITIONAL INFORMATION WAS PROVIDED: | | | | "SAFETY SIGNIFICANCE: LOSS OF ONE ADMINISTRATIVE CONTROL (SPACING), WHILE | | MAINTAINING THE SECOND ADMINISTRATIVE CONTROL (GEOMETRY). IT WOULD REQUIRE | | A VIOLATION OF BOTH CONTROLS TO PLACE URANIUM BEARING CONTAINERS IN A | | POSSIBLE CRITICAL CONFIGURATION." | | | | "POTENTIAL CRITICALITY PATHWAYS: POTENTIAL CRITICALITY PATHWAY WOULD | | INVOLVE THE LOSS OF BOTH ADMINISTRATIVE CONTROLS (SPACING AND GEOMETRY)." | | | | "CONTROLLED PARAMETERS: | | SPACING (ADMINISTRATIVE CONTROL) | | GEOMETRY (ADMINISTRATIVE CONTROL - 2S CYLINDERS IN A SAFE SLAB ARRAY; SMALL | | SAMPLE CONTAINERS IN A SAFE LINE ARRAY)." | | | | "ESTIMATED AMOUNT, ENRICHMENT: | | SAMPLE CONTAINERS IN SAFE LINE ARRAY TOTALED < 2 GRAMS U-235 @ 3% U-235 | | ENRICHMENT | | 17 2S CYLINDERS CONTAINED FROM 53 GRAMS TO 271 GRAMS U-235 WITH ENRICHMENT | | FROM 6.35% TO 18.77% U-235 (STORED IN SAFE SLAB ARRAY)." | | | | "NUCLEAR CRITICALITY SAFETY CONTROLS: | | (VIOLATED): ADMINISTRATIVE CONTROL OF 24" EDGE-TO-EDGE SPACING (SPACING | | WAS ò 18") | | (MAINTAINED): ADMINISTRATIVE CONTROL OF GEOMETRY OF THE SAFE LINE ARRAY | | AND THE SAFE SLAB ARRAY WAS MAINTAINED." | | | | "CORRECTIVE ACTIONS: THE 2S CYLINDERS WERE MOVED AWAY FROM THE SAFE LINE | | ARRAY (ONE-AT-A-TIME) TO ANOTHER STORAGE LOCATION, BRINGING THE STORAGE | | BACK INTO COMPLIANCE. THIS WAS PERFORMED WITHIN TWO HOURS OF DISCOVERY." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33211 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 11/04/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 15:35 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/04/97 | +------------------------------------------------+EVENT TIME: 14:48[EST]| |NRC NOTIFIED BY: SUSAN MUIK |LAST UPDATE DATE: 11/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEANNE HARRISON RDO | |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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONNECTICUT DEPARTMENT OF ENVIRONMENTAL PROTECTION (DEP) NOTIFIED OF 20 | | GALLON OIL SPILL ONSITE. | | | | "WHILE REMOVING OIL FROM THE MAIN TRANSFORMER TO PREPARE FOR LONG TERM | | STORAGE, THE TRANSFORMER WAS INADVERTENTLY OVERPRESSURIZED WITH NITROGEN. | | THIS RESULTED IN THE OIL RESERVOIR OF THE TRANSFORMER BURSTING AND OIL | | SPRAYING IN A 30 FOOT RADIUS. THE OIL CONTAINS NO PCBs (APPROXIMATELY 20 | | GALLONS OF OIL TOTAL). NO INJURIES RESULTED FROM THIS ACCIDENT. THE AREA | | HAS BEEN SECURED. THE COMPANY'S SPILL BRIGADE WAS CALLED. THEY ARE ON | | THEIR WAY FROM BEREIN, CT." | | | | | | THE LICENSEE INFORMED THE CONNECTICUT DEP AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33212 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 11/04/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 20:08 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 11/04/97 | +------------------------------------------------+EVENT TIME: 19:40[EST]| |NRC NOTIFIED BY: JEFF FOX |LAST UPDATE DATE: 11/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEANNE HARRISON RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SALT SERVICE WATER (SSW) PUMPS DECLARED INOPERABLE DUE TO NONCONSERVATIVE | | THERMAL OVERLOAD TRIP SETTINGS. | | | | THE LICENSEE DISCOVERED THAT THE THERMAL OVERLOAD TRIP SETTINGS OF THE SSW | | PUMP BREAKERS WAS SET TOO LOW (100%) UNDER DEGRADED VOLTAGE CONDITIONS. | | THERE ARE FIVE SSW PUMPS (2/LOOP AND 1 SWING) WHICH PROVIDE A HEAT SINK FOR | | THE CONTAINMENT COOLING SUBSYSTEM. THIS CONDITION WAS RECENTLY IDENTIFIED | | DURING TESTING AND EVALUATED BY ENGINEERING. THE LICENSEE HAS DECLARED ALL | | FIVE PUMPS INOPERABLE PLACING THE UNIT IN TECH SPEC LCO 3.5.B WHICH | | REQUIRES RESTORATION OF ONE LOOP OR BE IN COLD SHUTDOWN WITHIN 24 HOURS. | | REPLACEMENT THERMAL OVERLOADS WITH TRIP SETTINGS OF 115% ARE AVAILABLE AND | | ARE CURRENTLY BEING BENCH TESTED FOR REPLACEMENT IN THE FIVE SSW PUMP | | BREAKERS. MAINTENANCE ESTIMATES APPROXIMATELY 3-4 HOURS REPLACEMENT TIME | | PER PUMP BREAKER. THE LICENSEE WILL RESTORE BOTH SSW PUMPS FOR THE B LOOP | | INITIALLY EXITING THE 24 HOUR TECH SPEC LCO PLACING THE UNIT IN A LESS | | RESTRICTIVE 72 HOUR TECH SPEC LCO BASED ON THE 1940 EST DECLARATION OF SSW | | PUMP INOPERABILITY. | | | | THE LICENSEE INFORMED STATE AUTHORITIES AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+