U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/18/97 - 11/19/97 ** EVENT NUMBERS ** 32823 32824 32839 33261 33274 33275 33276 33277 33278 33279 33280 33281 33282 33283 33284 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32823 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 08/26/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 15:53 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/26/97 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 11/18/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN 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 +------------------------------------------------------------------------------+ | FAILURE OF A SAFETY REVIEW TO ADDRESS FINAL SAFETY ANALYSIS ATTRIBUTES ON | | ASSOCIATED COMPONENT COOLING WATER COOLING REQUIREMENTS | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "DURING THE ONGOING NRC [ARCHITECT-ENGINEER] DESIGN INSPECTION, A QUESTION | | WAS ASKED RELATIVE TO DUAL TRAIN COMPONENT COOLING WATER (CCW) SYSTEM | | OUTAGES. DURING DUAL TRAIN CCW OUTAGES, CCW COOLING IS SUPPLIED TO THE | | SPENT FUEL POOL (SFP) HEAT EXCHANGER ONLY FROM THE OPPOSITE UNIT. IF THAT | | UNIT HAS A LOSS OF COOLANT ACCIDENT (LOCA), CCW TO THE SFP HEAT EXCHANGER | | WILL ISOLATE. FINAL SAFETY ANALYSIS REPORT (FSAR) TABLE 9.5-2, FOOTNOTE 3, | | INDICATES THAT THE SFP HEAT EXCHANGER IS ASSUMED TO BE ON THE NON-ACCIDENT | | UNIT." | | | | THE LICENSEE REPORTED THE FOLLOWING INSPECTION QUESTIONS: | | | | "1) DOES A DUAL TRAIN CCW OUTAGE REPRESENT A CONDITION OUTSIDE THE PLANT | | DESIGN BASIS?" | | | | "2) WAS THIS REVIEWED AS PART OF THE PROCESS OF ALLOWING A DUAL TRAIN CCW | | OUTAGE?" | | | | "BASED ON A REVIEW OF FSAR TABLE 9.5-2, IT WAS CONCLUDED THAT FOOTNOTE 3 | | WAS ESTABLISHED TO CLARIFY WHY NO VALUES FOR SFP HEAT EXCHANGER FLOW FOR | | THE UNIT UNDERGOING THE LOCA ARE LISTED IN THE TABLE. FOOTNOTE 3 REFLECTS | | NORMAL SFP COOLING SYSTEM DESIGN AND OPERATION." | | | | "A REVIEW WAS PERFORMED OF THE SAFETY EVALUATION PERFORMED FOR THE UNIT 2 | | FULL CORE OFFLOAD WITH ONE TRAIN OF SPENT FUEL COOLING. THIS SAFETY REVIEW | | COVERED THE UNIT 2 REFUELING OUTAGE SCHEDULE WHICH INCLUDED A DUAL TRAIN | | CCW OUTAGE." | | | | "FOOTNOTE 3 OF TABLE 9.5-2 REPRESENTS THE NORMAL DESIGN OF THE SFP COOLING | | SYSTEM, THAT IS, THE SFP COOLING SYSTEM IS DESIGNED TO REMOVE THE HEAT | | GENERATED BY STORED SPENT FUEL ELEMENTS IN THE [SFP]. THE SYSTEM | | INCORPORATES TWO SEPARATE TRAINS." | | | | "THE SAFETY REVIEW FOR THE UNIT 2 FULL CORE OFFLOAD WITH ONE TRAIN OF SPENT | | FUEL COOLING ADDRESSED THE FSAR SECTION 9.4 ATTRIBUTE OF THE SFP COOLING | | DEALING WITH BULK POOL TEMPERATURE REQUIREMENTS; HOWEVER, THE SAFETY REVIEW | | FAILED TO ADDRESS FSAR SECTION 9.5 ATTRIBUTES ASSOCIATED CCW COOLING | | REQUIREMENTS AS GIVEN IN TABLE 9.5-2." | | | | " A CONDITION REPORT HAS BEEN WRITTEN TO INITIATE ACTIONS TO INVESTIGATE | | THIS EVENT AND PROVIDE PREVENTIVE ACTIONS." | | | | THIS ISSUE IMPACTS BOTH UNITS. HOWEVER, THE UNITS ARE NOT CURRENTLY IN A | | TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION AS A RESULT OF | | THIS ISSUE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 10/09/97 AT 0800 FROM PTACEK TO GOULD*** | | | | THE LICENSEE HAS DELETED THE WORDS "TIME TO BOIL EVENT AND" FROM THE | | CONCLUSION PARAGRAPH ADDRESSING THE SAFETY REVIEW SINCE ONLY BULK POOL | | TEMPERATURE REQUIREMENTS WERE ADDRESSED IN THE SAFETY REVIEW. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. THE R3DO | | (CLAYTON) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | | | | * * * UPDATE 1611 11/18/97 FROM PTACEK TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE FOLLOWING IS TEXT OF A | | FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "SUBSEQUENT INVESTIGATION INTO THIS CONDITION HAS CONCLUDED THAT CONTROLS | | IN PLACE WERE SUFFICIENT TO ENSURE THE PLANT REMAINED WITHIN ITS DESIGN | | BASIS RELATIVE TO SPENT FUEL POOL COOLING. THE SPENT FUEL POOL COOLING | | SYSTEM DESIGN REQUIREMENT IS TO MAINTAIN THE SPENT FUEL POOL BULK WATER | | TEMPERATURE BELOW 159.54øF ASSUMING A WORST CASE SCENARIO WITH ONE COOLING | | TRAIN OPERATIONAL. AN EVALUATION OF THE UNIT 2 REFUELING OUTAGE AND WORK | | BEING PERFORMED DETERMINED THAT THE SPENT FUEL POOL COOLING SYSTEM WAS | | CAPABLE OF PERFORMING ITS INTENDED SAFETY FUNCTION THROUGHOUT THE OUTAGE. | | BASED ON THIS, THE ORIGINAL NOTIFICATION IS BEING RETRACTED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED R3DO (MADERA). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32824 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 08/26/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 15:53 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/26/97 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 11/18/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN 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 +------------------------------------------------------------------------------+ | FAILURE TO PERFORM A 10 CFR 50.59 EVALUATION FOR A PROCEDURE CHANGE | | INVOLVING COMPONENT COOLING WATER HEAT EXCHANGER OUTLET TEMPERATURE LIMITS | | | | DURING THE ONGOING NRC ARCHITECT-ENGINEER DESIGN INSPECTION, A QUESTION WAS | | ASKED RELATIVE TO THE FACT THAT DURING THE LAST UNIT 2 REFUELING OUTAGE, AN | | ADMINISTRATIVE LIMIT OF 90øF WAS PLACED ON THE COMPONENT COOLING WATER | | (CCW) SYSTEM. THE THERMAL ANALYSIS INDICATED THAT A MAXIMUM CCW | | TEMPERATURE OF 90øF WOULD ELIMINATE ALL MARGIN ASSOCIATED WITH THE SPENT | | FUEL POOL (SFP) DESIGN ASSUMING A DESIGN FLOW OF 3,000 GPM. | | | | THE FOLLOWING INSPECTION QUESTION WAS ASKED: SINCE A CHANGE IN CCW | | TEMPERATURE WAS REQUIRED TO MEET THE FINAL SAFETY ANALYSIS REPORT (FSAR) | | VALUE OF 160øF FOR THE SFP, WAS A 10 CFR 50.59 UNREVIEWED SAFETY EVALUATION | | PERFORMED? | | | | THE LICENSEE REVIEWED THE CHANGE TO THE PROCEDURE TO LIMIT CCW TEMPERATURE | | TO 90øF. THE LICENSEE CONSIDERED THIS CHANGE TO BE AN ADMINISTRATIVE | | CHANGE ONLY TO LOWER THE ALLOWABLE TEMPERATURE TO THE SFP COOLING HEAT | | EXCHANGER. A 10 CFR 50.59 EVALUATION WAS NOT PERFORMED BECAUSE IT WAS NOT | | RECOGNIZED THAT THE 95øF REQUIREMENT WAS ESSENTIALLY BEING CHANGED. | | | | WITHOUT THE COMPLETION OF AN UNREVIEWED SAFETY QUESTION DETERMINATION, THE | | PLANT WAS IN A CONDITION OUTSIDE THE DESIGN BASIS. THE UNITS ARE NOT | | CURRENTLY IN A TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION AS | | A RESULT OF THIS ISSUE. | | | | A CONDITION REPORT HAS BEEN WRITTEN TO INITIATE ACTIONS TO INVESTIGATE THIS | | EVENT AND PROVIDE PREVENTIVE ACTIONS. THE 90øF LIMIT IS NO LONGER IN THE | | OPERATING PROCEDURES. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1611 11/18/97 FROM PTACEK TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE FOLLOWING IS TEXT OF A | | FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "SUBSEQUENT INVESTIGATION INTO THIS CONDITION HAS CONCLUDED THAT THE CCW | | SYSTEM TEMPORARY ADMINISTRATIVE TEMPERATURE LIMIT OF 90F WAS APPROPRIATELY | | REVIEWED BY THE UNREVIEWED SAFETY QUESTION DETERMINATION PERFORMED AT THE | | TIME. FURTHERMORE, IT HAS BEEN CONCLUDED THAT THE UNREVIEWED SAFETY | | QUESTION DETERMINATION PROVIDED ADEQUATE JUSTIFICATION THAT THE SPENT FUEL | | POOL AND THE COMPONENT COOLING WATER SYSTEM REMAINED WITHIN THE DESIGN | | BASIS DURING THE UNIT 2 1996 REFUELING OUTAGE. BASED ON THIS, THE ORIGINAL | | NOTIFICATION IS BEING RETRACTED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED R3DO (MADERA). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32839 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 08/28/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 16:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/28/97 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 11/18/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MIKE JORDAN RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 92 POWER OPERATION | 92 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AVAILABLE WATER VOLUME IN RWST NOT ADEQUATE IN MODES 5 AND 6 - | | | | DURING THE ONGOING NRC AE DESIGN INSPECTION, NRC INSPECTORS ASKED A | | QUESTION ABOUT THE REACTOR COOLANT MAKEUP REQUIRED AFTER A 10CFR50, | | APPENDIX R FIRE. TO RESPOND TO THE QUESTION, THE LICENSEE REVIEWED | | TWO ASSOCIATED DESIGN CALCULATIONS. THE MORE RESTRICTIVE CALCULATION | | WAS DETERMINED TO BE THE CALCULATION OF RECORD TO MEET THE REQUIREMENT. | | THIS CALCULATION REQUIRES 87,000 GALLONS OF WATER TO BE AVAILABLE IN THE | | REFUELING WATER STORAGE TANK (RWST). THE VALUE OF 87,000 GALLONS WAS | | APPROVED ON 02/20/90. DURING MODES 1 THROUGH 4, PLANT PROCEDURES | | ADEQUATELY ENSURE THAT THIS REQUIREMENT IS MET. DURING MODES 5 AND 6, | | PLANT PROCEDURES ARE NOT ADEQUATE TO ENSURE THAT THIS REQUIREMENT IS MET. | | THE PLANT HAS BEEN IN MODES 5 AND 6 MANY TIMES SINCE THIS REQUIREMENT | | BECAME EFFECTIVE ON 02/20/90. BASED ON THIS, THE PLANT HAS BEEN IN AN | | UNANALYZED CONDITION SEVERAL TIMES SINCE 02/20/90. | | | | CURRENTLY BOTH UNITS ARE IN MODE 1. THE LICENSEE IS REVIEWING PLANT | | OPERATING PROCEDURES TO DETERMINE IMPACT AND WILL IMPLEMENT PROCEDURE | | CHANGES AS NEEDED PRIOR TO EITHER UNIT ENTERING MODES 5 OR 6. THE LICENSEE | | IS CONTINUING TO EVALUATE THE SUBJECT CALCULATIONS AND PLANS TO SUBMIT A | | LICENSEE EVENT REPORT TO THE NRC ON THIS SUBJECT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1611 11/18/97 FROM PTACEK TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. | | | | "SUBSEQUENT INVESTIGATION INTO THIS CONDITION HAS CONCLUDED THAT THE | | APPROPRIATE CONTINGENCY ACTION HAD OCCURRED AS REQUIRED. BASED ON THIS, THE | | ORIGINAL NOTIFICATION IS BEING RETRACTED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED R3DO (MADERA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33261 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 11/14/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 15:48 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 11/14/97 | +------------------------------------------------+EVENT TIME: 15:16[EST]| |NRC NOTIFIED BY: WEAVER |LAST UPDATE DATE: 11/18/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EQUIPMENT DECLARED INOPERABLE DUE TO ENVIRONMENTAL QUALIFICATION CONCERNS | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "DURING ROUTINE WORK IN THE REACTOR BUILDING NORTH STAIRWELL, A PENETRATION | | TO THE NORTH AUXILIARY BAY FROM THE SECONDARY CONTAINMENT WAS DISCOVERED. | | THE HOLE IS APPROXIMATELY 6"x 8" IN SIZE. DUE TO EQ [ENVIRONMENTAL | | QUALIFICATION] CONCERNS, THE EQUIPMENT WITHIN THE NORTH AUXILIARY BAY WAS | | DECLARED INOPERABLE AND THE APPLICABLE TECHNICAL SPECIFICATIONS WERE | | ENTERED. THIS CONDITION APPEARS TO HAVE EXISTED SINCE ORIGINAL | | CONSTRUCTION. WORK IS UNDERWAY TO SEAL THE PENETRATION." | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | | | | ***UPDATE AT 0946 ON 11/18/97 BY TUTTLE TO GOULD*** | | | | THIS UPDATE IS TO CLARIFY THE INITIAL NOTIFICATION. THE DESCRIPTION READS | | AS FOLLOWS: "DURING ROUTINE WORK IN THE REACTOR BUILDING NORTH STAIR | | TOWER, AN OPEN PENETRATION BETWEEN THE NORTH AUXILIARY BAY AND THE STAIR | | TOWER WAS DISCOVERED. BOTH AREAS ARE WITHIN THE SECONDARY CONTAINMENT | | BOUNDARY, THEREFORE THE OPEN PENETRATION DID NOT EFFECT SECONDARY | | CONTAINMENT INTEGRITY. EQ REQUIREMENTS IN THE NORTH AUXILIARY BAY COULD | | NOT BE IMMEDIATELY VERIFIED BY ENGINEERING AND THE SSS DECLARED THE | | EQUIPMENT WITHIN THE NORTH AUXILIARY BAY INOPERABLE AND THE APPLICABLE | | TECHNICAL SPECIFICATIONS WERE ENTERED. THIS CONDITION APPEARS TO HAVE | | EXISTED SINCE ORIGINAL CONSTRUCTION." AT 0100 ON 11/15/97 THE PENETRATION | | WAS SEALED AND THE EQUIPMENT IN THE AREA DECLARED OPERABLE. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. THE REG 1 RDO(MCFADDEN) WAS | | NOTIFIED BY THE HOO. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33274 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 11/18/97 | |UNIT: [2] [3] [ ] STATE: PA |NOTIFICATION TIME: 09:04 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 11/17/97 | +------------------------------------------------+EVENT TIME: 10:07[EST]| |NRC NOTIFIED BY: BIRD |LAST UPDATE DATE: 11/18/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK MCFADDEN 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 93 POWER OPERATION | 93 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DENIED UNESCORTED ACCESS TO A MEMBER OF THEIR NON-LICENSED | | MANAGEMENT BECAUSE OF FAILURE OF RANDOM DRUG/ALCOHOL TEST. | | | | THE INDIVIDUAL WAS SUBJECTED TO RANDOM DRUG AND ALCOHOL TESTS. INITIAL | | ALCOHOL TESTING WAS PERFORMED AT 1007 AND 1009 WITH THE INDIVIDUAL HAVING A | | BREATH ALCOHOL CONTENT INDICATING A BLOOD ALCOHOL CONCENTRATION > 0.04%. | | CONFIRMATORY TEST WERE PERFORMED AT 1015 AND 1018 WITH SIMILAR RESULTS. THE | | INDIVIDUAL ALSO LOST HIS UNESCORTED ACCESS TO LIMERICK. | | | | THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33275 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 11/18/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 10:13 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/17/97 | +------------------------------------------------+EVENT TIME: 15:00[EST]| |NRC NOTIFIED BY: FREEMAN |LAST UPDATE DATE: 11/18/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK MCFADDEN RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 LICENSEE REMOVED A DEAD SEAL FROM THE SERVICE WATER SYSTEM PUMP HOUSE | | FOREBAY. | | | | THE SEAL WAS DISCOVERED 11/17/97, BUT WAS NOT REMOVED UNTIL 11/18/97 @ | | 0900. THIS 24HR NOTIFICATION IS BEING MADE IN ACCORDANCE WITH SECTION 4.1 | | OF THE ENVIRONMENTAL PROTECTION PLAN, APPENDIX B OF THE TS. THE NATIONAL | | MARINE FISHERIES SERVICE WILL BE NOTIFIED. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33276 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 11/18/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 11:43 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/17/97 | +------------------------------------------------+EVENT TIME: 15:25[CST]| |NRC NOTIFIED BY: WINGATE |LAST UPDATE DATE: 11/18/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED STATE REGARDING RELEASE OF WATER TO LAKE MICHIGAN | | | | THE LICENSEE NOTIFIED THE WISCONSIN STATE DEPARTMENT OF NATURAL RESOURCES | | REGARDING THE DISCHARGE OF APPROXIMATELY 8,800 GALLONS OF NONRADIOACTIVE | | WATER TO LAKE MICHIGAN. AT 1525 ON 11/17/97, A REPAIR COUPLING ON PIPING | | BETWEEN A NONRADIOACTIVE EFFLUENT SUMP AND THE RETENTION POND WAS DAMAGED | | WHEN STRUCK BY CONSTRUCTION EQUIPMENT. THIS DAMAGE PERMITTED WATER FROM THE | | SUMP TO BYPASS THE POND. THE LICENSEE IMMEDIATELY SECURED THE EFFLUENT SUMP | | PUMPS, AND SUBMERSIBLE PUMPS WERE USED TO DIVERT WATER TO THE STORM DRAINS. | | THE LICENSEE SAMPLED THE EFFLUENT, BUT FOUND NO RADIOACTIVITY. | | | | THE COUPLING WAS REPAIRED, AND THE NORMAL EFFLUENT SUMP FLOW WAS RESTORED | | BY 1725 ON 11/17/97. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33277 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 11/18/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 12:37 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/18/97 | +------------------------------------------------+EVENT TIME: 11:45[EST]| |NRC NOTIFIED BY: PAUL FREEMAN |LAST UPDATE DATE: 11/18/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |MIKE MODES, R1 IAT | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 SECURITY EVENT - | | | | UNAUTHORIZED ENTRY INTO PLANT PROTECTED AREA BY AN UNIDENTIFIED DELIVERY | | PERSON. COMPENSATORY MEASURES HAVE BEEN IMPLEMENTED AND ADDITIONAL | | MEASURES ARE BEING TAKEN. THE LICENSEE WILL INFORM THE NRC RESIDENT | | INSPECTOR. REFER TO THE HOO LOG FOR ADDITIONAL DETAILS. | | | | * * * UPDATE AT 1515 ON 11/18/97 FROM R. STRICKLAND TAKEN BY JOLLIFFE * * * | | | | UPON FURTHER INVESTIGATION, THE LICENSEE HAS DOWNGRADED THIS EVENT FROM | | A ONE HOUR SECURITY EVENT TO A LOGGABLE SECURITY EVENT AND THUS, DESIRES | | TO RETRACT THIS EVENT. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | THE OPERATIONS OFFICER NOTIFIED THE R1 IAT MEMBER MIKE MODES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33278 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/18/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 12:35 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/15/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/18/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JOHN MADERA RDO | | DOCKET: 0707002 |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KIETH VANDERPOOL | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT | | | | "ON 11/15/97, AT 1030, IT WAS DISCOVERED THAT A NUCLEAR CRITICALITY SAFETY | | APPROVAL (NCSA) REQUIREMENT WAS NOT BEING MET IN THE X-326 HIGH ASSAY | | SAMPLING AREA (HASA) VAULT. NCSA-PLANT 048.A.00 LISTS TWO NUCLEAR | | CRITICALITY SAFETY CONTROLS. THE FIRST CONTROL, WHICH IS ADMINISTRATIVE, | | REQUIRES SPACING BETWEEN THE ITEMS IF THERE IS A HIDDEN CAVITY WITH A | | POTENTIAL VOLUME, AND THE SECOND CONTROL, WHICH IS ADMINISTRATIVE, INVOLVES | | MODERATION. THE FIRST CONTROL WAS VIOLATED WHEN THE ITEMS WERE STORED | | TOGETHER UNDER THE MINIMUM REQUIREMENT OF TWO FEET. THE SECOND CONTROL, | | MODERATION, WAS MAINTAINED THROUGHOUT THIS EVENT. THE LOSS OF ONE CONTROL, | | SPACING, MAKES THIS EVENT REPORTABLE TO THE NRC VIA 24-HOUR EVENT | | NOTIFICATION PER NUCLEAR REGULATORY EVENT REPORTING PROCEDURE UE2.RA.RE1030 | | APPENDIX D, CRITERIA A PARAGRAPH 4A. THERE WAS NO RELEASE OF RADIOACTIVE | | MATERIALS OR RADIOLOGICAL CONTAMINATION EXPOSURE ASSOCIATED WITH THIS | | EVENT. | | | | AS A SPECIAL NOTE, AT THE TIME THIS EVENT OCCURRED, IT WAS DETERMINED THAT | | THIS CONDITION WAS NOT REPORTABLE BECAUSE CRITICALITY COULD NOT OCCUR. | | HOWEVER, ON 11/17/97, AFTER FURTHER EVALUATION, IT WAS DETERMINED THIS | | EVENT WAS REPORTABLE BECAUSE A LOSS OF ONE OF TWO CONTROLS EXISTED. THE NRC | | RESIDENT INSPECTOR HAS BEEN NOTIFIED OF THIS EVENT." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33279 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 11/18/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 14:52 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/18/97 | +------------------------------------------------+EVENT TIME: 10:00[EST]| |NRC NOTIFIED BY: BRIAN CROKE |LAST UPDATE DATE: 11/18/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK MCFADDEN 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 +------------------------------------------------------------------------------+ | -SW VLV CLOSED TO PREVENT DRAINING COOLING TOWER BASIN DURING SEISMIC EVENT | | | | VERMONT YANKEE UFSAR SECTION 10.8 STATES THAT SEISMIC EFFECTS WILL NOT | | IMPAIR THE ABILITY OF THE ALTERNATE COOLING (AC) SYSTEM TO ACCOMMODATE | | ON-SITE WATER STORAGE REQUIREMENTS IN THE EVENT OF A LOSS OF THE VERNON | | POND (ULTIMATE HEAT SINK) FOR ONE WEEK. | | | | IN ADDITION, UFSAR SECTION 10.8.3 STATES THAT DRAINING THE COOLING TOWER | | BASIN (CTB) WOULD REQUIRE DELIBERATE MANUAL ACTIONS TO BE TAKEN. THIS | | PROVISION PROVIDES FURTHER ASSURANCE THAT THE CTB WILL ALWAYS REMAIN FULL | | UNTIL THE AC SYSTEM IS PLACED INTO OPERATION. | | | | IF THE NON-SEISMIC PORTION OF THE SW SYSTEM RETURN LINE TO EITHER THE | | CIRCULATING WATER SYSTEM DISCHARGE OR THE COOLING TOWERS, WERE TO BREAK | | WHILE THE DEEP CTB IS IN THE DEICING MODE, AND PRIOR TO CLOSURE OF THE | | REACTOR BUILDING SW SYSTEM DISCHARGE HEADER ISOLATION VALVE #SW-18, AN | | UNANALYZED LOSS OF INVENTORY FROM THE DEEP CTB WOULD OCCUR. | | | | THIS CONDITION COULD COMPROMISE THE UFSAR SECTION 10.8.2 SEVEN-DAY | | INVENTORY REQUIREMENT FOR THE DECAY HEAT/RESIDUAL HEAT REMOVAL SYSTEM. | | | | THE LICENSEE HAS CLOSED THE SW SYSTEM DISCHARGE VALVE TO THE CTB, #SW-11, | | UNTIL LONG TERM CORRECTIVE ACTIONS CAN BE DETERMINED. RETENTION OF VALVE | | #SW-11 IN THE CLOSED POSITION WILL PREVENT ANY LOSS OF CTB INVENTORY. PLANT | | OPERATORS WILL ROUTINELY CHECK THE DEEP CTB FOR PROPER WATER LEVEL AND THE | | EXISTENCE OF ICE OR DEBRIS ONCE EVERY EIGHT HOURS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33280 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/18/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:22 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/16/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 07:00[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/18/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JOHN MADERA RDO | | DOCKET: 0707002 |JOE HOLONICH, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KEITH VANDERPOOL | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 24 HOUR NRC BULLETIN 91-01 REPORT - | | | | AT 0700 ON 11/16/97, THE LICENSEE DISCOVERED THAT A NUCLEAR CRITICALITY | | SAFETY APPROVAL (NCSA) REQUIREMENT WAS NOT BEING MET IN AN AREA NEAR THE | | X-344 TOLL ENRICHMENT FACILITY WHERE LARGE UF6 CYLINDERS ARE STORED. | | | | NCSA-PLANT 004.A01, PART B, ITEM #11, STATES THAT LARGE UF6 CYLINDERS | | (2.5, 10, AND 14 TON) WHICH CONTAIN GREATER THAN 1.0% ENRICHMENT, AND | | GREATER THAN OR EQUAL TO 50 POUNDS URANIUM MASS SHALL NOT BE STACKED, AND | | A SPACING OF AT LEAST 20 FEET SHALL BE MAINTAINED BETWEEN STACKED ARRAYS | | OF HEEL QUANTITY CYLINDERS (CONTAINING LESS THAN 50 POUNDS URANIUM MASS) | | AND OTHER FULL UF6 CYLINDERS CONTAINING ENRICHED URANIUM. | | | | THIS CONTROL WAS LOST WHEN TWO UF6 CYLINDERS, EACH CONTAINING GREATER THAN | | 50 POUNDS URANIUM MASS, WERE FOUND IN A STACKED ARRAY, AND THE POTENTIAL | | EXISTED FOR A FULL UF6 CYLINDER TO HAVE BEEN MOVED TO WITHIN 20 FEET OF A | | STACKED ARRAY OF HEELED CYLINDERS. THE LICENSEE HAS DETERMINED THAT NO | | OTHER SIMILAR CYLINDERS ARE STORED IN THIS CONFIGURATION. | | | | AT 1740 ON 11/17/97, THE LICENSEE DETERMINED THAT THE LOSS OF THIS CONTROL | | MAKES THIS EVENT REPORTABLE TO THE NRC AS A 24 HOUR NRC BULLETIN 91-01 | | EVENT. | | | | THERE WAS NO RELEASE OF HAZARDOUS MATERIALS OR RADIOLOGICAL EXPOSURE | | ASSOCIATED WITH THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33281 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 11/18/97 | |UNIT: [1] [2] [ ] STATE: SC |NOTIFICATION TIME: 16:26 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/18/97 | +------------------------------------------------+EVENT TIME: 15:55[EST]| |NRC NOTIFIED BY: KEN BEAVER |LAST UPDATE DATE: 11/18/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR OVERFILLING STEAM GENERATOR DURING POSTULATED ACCIDENT | | | | "DURING A DESIGN REVIEW, ENGINEERING IDENTIFIED A SCENARIO WHICH HAS THE | | POTENTIAL TO BE MORE LIMITING THAN THE SCENARIO CONSIDERED IN THE EXISTING | | LICENSING BASIS. | | | | "THE SCENARIO INVOLVES A FAILURE OF 125 VDC VITAL I&C DISTRIBUTION CENTER | | EDE OR EDF COINCIDENT WITH A LOSS OF OFFSITE POWER AND A STEAM GENERATOR | | TUBE RUPTURE. LOSS OF ONE OF THE DISTRIBUTION CENTERS RESULTS IN THE | | INABILITY TO ISOLATE AUXILIARY FEEDWATER FLOW FROM THE CONTROL ROOM TO TWO | | STEAM GENERATORS. IN ADDITION, A FAILURE OF EDE WOULD PREVENT CLOSURE OF | | THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP TRIP AND THROTTLE VALVE SA145 | | FROM THE MAIN CONTROL ROOM. SHOULD A STEAM GENERATOR TUBE RUPTURE OCCUR ON | | ONE OF THE AFFECTED STEAM GENERATORS, THERE IS A POTENTIAL TO OVERFILL THE | | STEAM GENERATOR BECAUSE AUXILIARY FEEDWATER FLOW CANNOT BE REMOTELY | | ISOLATED. | | | | "THE UFSAR CHAPTER 15 STEAM GENERATOR TUBE RUPTURE ANALYSIS ASSUMES THAT | | OPERATORS IN THE CONTROL ROOM ISOLATE AUXILIARY FEEDWATER FLOW TO A | | RUPTURED STEAM GENERATOR PRIOR TO STEAM GENERATOR OVERFILL. EXISTING | | EMERGENCY OPERATING PROCEDURES PROVIDE FOR MANUAL CLOSURE OF THE AFFECTED | | AUXILIARY FEEDWATER FLOW CONTROL VALVES; HOWEVER, IT MAY NOT BE POSSIBLE TO | | ACCOMPLISH THIS PRIOR TO OVERFILL OCCURRING. | | | | "CONSERVATIVE ADMINISTRATIVE CONTROLS HAVE BEEN PUT INTO PLACE LIMITING | | REACTOR COOLANT DOSE EQUIVALENT IODINE TO ENSURE THE CONSEQUENCES OF THE | | CHAPTER 15 STEAM GENERATOR TUBE RUPTURE ANALYSIS REMAIN BOUNDING. THE | | RESTRICTIONS ON DOSE EQUIVALENT IODINE COUPLED WITH THE LOW PROBABILITY OF | | THIS SCENARIO OCCURRING PROVIDE ASSURANCE THAT DOSES ARE ACCEPTABLE. | | CURRENT PLANT DOSE EQUIVALENT IODINE LEVELS ARE APPROXIMATELY AN ORDER OF | | MAGNITUDE BELOW THE NEW ADMINISTRATIVE VALUES. AN EVALUATION OF THIS | | SCENARIO IS IN PROGRESS AND CORRECTIVE ACTIONS WILL BE DEVELOPED BASED ON | | THE OUTCOME OF THIS EVALUATION." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 33282 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: HALLIBURTON ENERGY SERVICES |NOTIFICATION DATE: 11/18/97 | | CITY: DUNCAN REGION: 4 |NOTIFICATION TIME: 17:46 [ET]| | COUNTY: STATE: OK |EVENT DATE: 11/18/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:01[CST]| | DOCKET: |LAST UPDATE DATE: 11/18/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOSEPH TAPIA RDO | | |JOE HOLONICH, NMSS EO | +------------------------------------------------+LINDA HOWELL R4 | |NRC NOTIFIED BY: STEVE WOODS | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBDB 30.50(b)(4)(ii) DAMAGED LNM/CONTAINER | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE RECEIVED LEAKING SOURCE FROM VENDOR | | | | THE LICENSEE REPORTED THAT A PACKAGE RECEIVED FROM ISOTOPE PRODUCT | | LABORATORIES, 1800 N. KEYSTONE ST., BURBANK, CA, CONTAINED A DAMAGED | | 10 mCi Cs-137 SOURCE. THE LICENSEE REPORTED THAT THE EXTERIOR OF THE | | PACKAGE HAD NO REMOVABLE CONTAMINATION, BUT APPROXIMATELY 0.27 æCi OF | | ACTIVITY WAS REMOVED FROM THE SURFACE OF THE SOURCE TUBE. THE LICENSEE | | HAS CONTACTED THE VENDOR AND IS MAKING ARRANGEMENTS TO RETURN THE DAMAGED | | SOURCE TO THE VENDOR. | | | | NOTE: SEE HOO LOG FOR CONTACT TELEPHONE NUMBERS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33283 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 11/18/97 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 17:52 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/18/97 | +------------------------------------------------+EVENT TIME: 16:55[EST]| |NRC NOTIFIED BY: WATTS |LAST UPDATE DATE: 11/18/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE 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 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC GROUP 1 (MSIV) ISOLATION DURING PLANT SHUTDOWN | | | | WHILE COOLING DOWN THE REACTOR FOLLOWING A MANUAL REACTOR SCRAM, A FULL | | GROUP 1 (MAIN STEAM ISOLATION VALVE) ISOLATION WAS RECEIVED DUE TO LOW | | CONDENSER VACUUM. THE INBOARD MSIVs WERE ALREADY CLOSED TO CONTROL THE | | COOLDOWN RATE AT THE TIME OF THE EVENT. THE LICENSEE REPORTED THAT | | OPERATORS FAILED TO BLOCK THE MAIN CONDENSER VACUUM - LOW PRESSURE | | ISOLATION LOGIC BEFORE BREAKING CONDENSER VACUUM. THE GROUP 1 ISOLATION | | SIGNAL HAS BEEN RESET. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33284 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 11/18/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:23 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 11/18/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:15[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/18/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y | | | DOCKET: 0707001 |JOE HOLONICH, NMSS EO | +------------------------------------------------+JIM CREED, IAT R3 | |NRC NOTIFIED BY: BILL HALICKS | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - GASEOUS DIFFUSION PLANT SECURITY EVENT - | | | | DISCOVERY OF LOSS OF CONTROL OF CLASSIFIED DOCUMENTS. COMPENSATORY | | MEASURES HAVE BEEN TAKEN AND AN INVESTIGATION IS UNDERWAY. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG FOR ADDITIONAL | | DETAILS. | +------------------------------------------------------------------------------+