U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/23/96 - 12/24/96 ** EVENT NUMBERS ** 31500 31501 31502 31503 31504 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31500 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 12/23/96 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 11:20 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 12/23/96 | +------------------------------------------------+EVENT TIME: 09:00[EST]| |NRC NOTIFIED BY: BURCHFIELD |LAST UPDATE DATE: 12/23/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BARR 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT ISOLATION VALVE INOPERABLE IN PAST DUE TO INSUFFICIENT THRUST | | SETTING. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "2HP-20 IS A MOTOR-OPERATED, CONTAINMENT ISOLATION VALVE. 2HP-20 IS | | REQUIRED TO CLOSE DURING AN ENGINEERED SAFEGUARDS ACTUATION TO ENSURE THAT | | CONTAINMENT INTEGRITY EXISTS FOR CERTAIN DESIGN BASIS ACCIDENTS. | | | | AS A FOLLOW UP ITEM TO GL 89-10, ONS HAS HAD A PROGRAM IN PLACE TO INSPECT | | DOUBLE DISC ISOLATION VALVES TO DETERMINE WHETHER THE LOWER WEDGE IS | | INSTALLED IN THE PREFERRED DIRECTION. ON NOVEMBER 26, 1996, IT WAS | | DISCOVERED THAT THE LOWER WEDGE IN 2HP-20 WAS INSTALLED IN THE | | NON-PREFERRED DIRECTION. REPAIRS WERE COMPLETED TO 2HP-20 ON NOVEMBER 30, | | 1996. THEREFORE, THE VALVE IS PRESENTLY OPERABLE, AND THE AFFECTED | | CONTAINMENT PENETRATION IS PRESENTLY OPERABLE. | | | | A PAST OPERABILITY EVALUATION WAS PERFORMED ON 2HP-20 FROM THE TIME THE | | VALVE WAS ORIGINALLY INSTALLED ON MARCH 5, 1992. THE AS-LEFT CONTROL SWITCH | | TRIP SETTING OF 2HP-20 WAS DETERMINED TO BE LESS THAN THE THRUST REQUIRED | | TO CLOSE THE VALVE, ASSUMING THAT THE LOWER WEDGE WAS INSTALLED IN THE | | NON-PREFERRED DIRECTION. AS A RESULT, ON DECEMBER 23, 1996, IT WAS | | CONCLUDED THAT THE VALVE WOULD NOT HAVE BEEN CAPABLE OF PROVIDING | | CONTAINMENT ISOLATION DURING AN ENGINEERED SAFEGUARDS ACTUATION. THEREFORE, | | THE AFFECTED CONTAINMENT PENETRATION PATH WAS ALSO DECLARED INOPERABLE | | SINCE THE STATED DESIGN REQUIREMENT OF UFSAR SECTION 6.2.3.2 WAS NOT MET. | | | | THE PAST INOPERABILITY EXISTED FROM MARCH 5, 1992, DURING THE PERIODS WHEN | | 2HP-20 WAS OPEN." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31501 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 12/23/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:28 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 12/23/96 | +------------------------------------------------+EVENT TIME: 10:32[EST]| |NRC NOTIFIED BY: MIKE MICKLOW |LAST UPDATE DATE: 12/23/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL RDO | |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 +------------------------------------------------------------------------------+ | DISCOVERY OF THE POTENTIAL FOR A THERMALLY INDUCED OVERPRESSURE TRANSIENT | | RESULTING IN THE RUPTURE OF THE CHARCOAL FILTER DOUSING PIPING (WHICH IS | | SUPPLIED BY THE CONTAINMENT SPRAY HEADER) | | | | DURING A REVIEW OF NRC GENERIC LETTER 96-06, IT WAS IDENTIFIED THAT THE | | CONTAINMENT CHARCOAL FILTER DOUSING LINE (WHICH IS SUPPLIED BY THE | | CONTAINMENT SPRAY HEADER) COULD BE SUBJECT TO OVERPRESSURIZATION DURING A | | DESIGN BASIS LOSS OF COOLANT ACCIDENT OR STEAM BREAK EVENT. SUCH AN | | OVERPRESSURIZATION COULD RENDER BOTH TRAINS OF CONTAINMENT SPRAY | | INOPERABLE. SINCE THE DOUSING FUNCTION IS NOT CREDITED IN THE GINNA | | ACCIDENT ANALYSIS, THE DOUSING HEADER LINE WAS ISOLATED AT 0017 ON DECEMBER | | 21, 1996, TO SEPARATE IT FROM THE CONTAINMENT SPRAY SYSTEM. THIS | | ELIMINATED THE POTENTIAL FOR SPRAY SYSTEM INOPERABILITY. THE REVIEW OF THE | | OVERPRESSURIZATION CONCERN WAS COMPLETED ON DECEMBER 23, 1996, AND | | NOTIFICATION WAS MADE TO THE SHIFT SUPERVISOR AT 1032. CALCULATIONS SHOWED | | THAT A THERMALLY INDUCED OVERPRESSURE TRANSIENT RESULTING IN THE RUPTURE OF | | THE CHARCOAL FILTER DOUSING PIPING WAS POSSIBLE. THE UNIT IS NOT CURRENTLY | | IN A TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION AS A RESULT | | OF THIS ISSUE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31502 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 12/23/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 12:56 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 12/21/96 | +------------------------------------------------+EVENT TIME: 10:25[EST]| |NRC NOTIFIED BY: GUNTIS GONCAROVS |LAST UPDATE DATE: 12/23/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INFORMATION REPORT OF A NOTIFICATION TO A STATE ENVIRONMENTAL AGENCY DUE TO | | HIGH IRON CONCENTRATION IN A SAMPLE TAKEN FROM A TURBINE HALL FLOOR DRAIN | | | | THIS INCIDENT OCCURRED AT 1025 ON DECEMBER 21, 1996. THE ANALYSIS OF A | | SAMPLE TAKEN FROM A TURBINE HALL FLOOR DRAIN INDICATED THAT THE SAMPLE | | EXCEEDED THE NATIONAL POLLUTANT DISCHARGE ELIMINATION SERVICE (NPDES) | | CONCENTRATION PERMIT LIMIT FOR IRON BY MORE THAN A FACTOR OF 1.5 TIMES. THE | | CONCENTRATION OF IRON DISCHARGED ACCORDING TO THIS SAMPLE WAS 1.118 PARTS | | PER MILLION, AND THE MAXIMUM DAILY NPDES LIMIT WAS 0.67 PARTS PER MILLION. | | THE FLOOR DRAIN LEADS TO THE DISCHARGE CANAL WHICH EVENTUALLY FLOWS INTO | | THE CONNECTICUT RIVER. THERE WAS NO RADIOACTIVITY IN THIS SAMPLE. | | | | THE LICENSEE HAS SAMPLED ALL INPUTS TO THE FLOOR DRAINS TO DETERMINE | | CONCENTRATIONS OF IRON AND pH VALUE. THE LICENSEE ALSO PLANS TO CHANGE THE | | POST-FILTER FOR THE AFFECTED SUMP. | | | | PER PROCEDURE, THE LICENSEE NOTIFIED THE STATE DEPARTMENT OF ENVIRONMENTAL | | PROTECTION ON DECEMBER 23, 1996, AND PLANS TO PROVIDE A LETTER TO THE STATE | | DEPARTMENT OF ENVIRONMENTAL PROTECTION WITHIN 5 DAYS. (THE NOTIFICATION FOR | | THIS TYPE OF EVENT WAS REQUIRED TO BE MADE TO THE STATE DURING NORMAL | | BUSINESS HOURS.) THE LICENSEE ALSO NOTIFIED THE NRC RESIDENT INSPECTOR. | | (REFER TO THE HOO LOG FOR A SITE CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31503 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 12/23/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:52 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 12/23/96 | +------------------------------------------------+EVENT TIME: 15:10[CST]| |NRC NOTIFIED BY: BOB SVALESON |LAST UPDATE DATE: 12/23/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DISCOVERY THAT THE ORIGINAL FINAL SAFETY ANALYSIS REPORT (FSAR) VALUE OF | | ONE FOOT DIFFERENTIAL PRESSURE ACROSS THE EMERGENCY CORE COOLING SYSTEM | | (ECCS) SUCTION STRAINERS WAS INCORRECT (REFER TO EVENT NUMBER 31495 FOR A | | SIMILAR EVENT THAT WAS REPORTED BY DRESDEN ON DECEMBER 20, 1996.) | | | | ON DECEMBER 20, 1996, IT WAS DISCOVERED THAT THE ORIGINAL VALUE OF ONE FOOT | | DIFFERENTIAL PRESSURE ACROSS THE ECCS SUCTION STRAINERS UTILIZED IN THE | | FSAR WAS NOT CORRECT. CURRENTLY, CALCULATIONS SHOW THAT THE DESIGN | | FUNCTIONS OF THE ECCS SYSTEMS ARE MET. IN THIS INITIAL ANALYSIS, A VALUE | | OF CONTAINMENT OVERPRESSURE WAS USED THAT IS SLIGHTLY GREATER THAN THAT | | SHOWN IN THE FSAR. CONTINUED ANALYSIS IS EXPECTED TO SHOW THAT THE | | LICENSEE MAY MEET THE LONG-TERM PUMP FLOW REQUIREMENTS WITHOUT THE | | ADDITIONAL MARGIN THAT WAS UTILIZED IN THE ANALYSIS. HOWEVER, SINCE THE | | MARGIN IS SMALL, THE LICENSEE HAS ELECTED TO MAKE THIS NOTIFICATION. | | ADDITIONAL EVALUATIONS ARE CURRENTLY ONGOING. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31504 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 12/23/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 22:44 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 12/23/96 | +------------------------------------------------+EVENT TIME: 18:43[CST]| |NRC NOTIFIED BY: KYLE DITTMAN |LAST UPDATE DATE: 12/23/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC ACTUATION OF THE REACTOR PROTECTION SYSTEM (RPS) DUE TO HIGH | | WATER LEVEL IN THE SCRAM DISCHARGE VOLUME (SDV) DURING A REFUELING OUTAGE | | | | AT 1843 CST, AN AUTOMATIC RPS ACTUATION OCCURRED DUE TO HIGH WATER LEVEL IN | | THE SDV. AT THE TIME OF THIS EVENT, THE UNIT WAS SHUT DOWN FOR REFUELING | | OUTAGE #6 (RF-6) WITH ALL CONTROL RODS IN THEIR FULL IN POSITION. THERE | | WAS NO ROD MOVEMENT DUE TO THE SCRAM SIGNAL, AND ALL SYSTEMS FUNCTIONED AS | | REQUIRED. | | | | A REPAIRMAN WAS ATTEMPTING TO REPAIR A PREVIOUSLY IDENTIFIED AIR LEAK ON | | CONTROL ROD HYDRAULIC POWER UNIT (HCU) #44-49 WHEN THE AIR LINE BROKE FREE. | | THE AIR LINE BROKE BEHIND THE COMPRESSION FITTING WHICH CAUSED THE AIR | | HEADER TO THE CONTROL ROD SCRAM VALVES AND THE SDV VENTS AND DRAINS TO | | DEPRESSURIZE. WHEN THE AIR HEADER DEPRESSURIZED, THE SCRAM VALVES OPENED, | | AND THE SDV VENTS AND DRAINS CLOSED AS DESIGNED. WITH THE SDV VENTS AND | | DRAINS CLOSED, THE SDV FILLED UP WITH WATER CAUSING A VALID RPS ACTUATION. | | THE RPS ACTUATION OCCURRED AFTER THE CONTROL ROD SCRAM VALVES WERE ALREADY | | OPEN. THE BROKEN AIR LINE WAS REPAIRED, AND THE RPS ACTUATION SIGNAL WAS | | RESET AT 1935 CST. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+