U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/07/98 - 10/08/98 ** EVENT NUMBERS ** 34856 34881 34882 34883 34884 34885 34886 34887 34888 34889 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34856 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 09/30/98 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 14:09 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 09/30/98 | +------------------------------------------------+EVENT TIME: 13:20[EDT]| |NRC NOTIFIED BY: JOHN SCHORK |LAST UPDATE DATE: 10/07/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN CARUSO 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 +------------------------------------------------------------------------------+ | IMPROPERLY INSTALLED THERMOLAG FIRE BARRIER | | | | DURING THE REMOVAL OF THERMOLAG MATERIAL, A FIRE RESISTANT MATERIAL THAT | | WAS INSTALLED IN 1987 TO MEET THE REQUIREMENTS OF 10 CFR PART 50, APPENDIX | | R, WORKERS OBSERVED THAT SEVERAL PORTIONS OF FIRE BARRIER "1 FHC-FB-06" | | LOCATED IN FIRE ZONE FH-FZ-1 IN THE 281' ELEVATION OF THE TMI-1 FUEL | | HANDLING BUILDING DID NOT HAVE REQUIRED FILLET OF TROWEL GRADE MATERIAL | | 330-1. THE THERMOLAG WAS BEING INSPECTED IN PREPARATION FOR ITS REPLACEMENT | | WITH MECATISS. | | | | THE CONTROL ROOM WAS NOTIFIED AND A FIRE WATCH WAS POSTED IN ACCORDANCE | | WITH THE SITE FIRE PROTECTION PROGRAM PROCEDURE. REPAIRS WERE MADE TO THE | | NONCONFORMING SEAMS. AT 1320, THE PLANT REVIEW GROUP CONCLUDED A REVIEW OF | | THE NONCONFORMING CONDITION AND DETERMINED THAT THE CONDITION WAS | | IMMEDIATELY REPORTABLE TO THE NRC IN ACCORDANCE WITH 10CFR50.72(b)(1)(ii) | | AS A CONDITION OUTSIDE OF THE DESIGN BASIS OF THE PLANT AND AS A SUPPLEMENT | | TO EARLIER SIMILAR NOTIFICATIONS. THE CONDITION WAS DETERMINED TO BE | | REPORTABLE BECAUSE THE FIRE BARRIER DID NOT CONFORM TO ITS DESIGN BASIS AND | | THERE WAS REASONABLE JUSTIFICATION THAT THE NONCONFORMING CONDITION WAS NOT | | THE RESULT OF AGE-RELATED DEGRADATION BUT RATHER AN INCORRECT INSTALLATION. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE ON 10/01/98 AT 1512 ET BY JOHN SCHORK TAKEN BY MACKINNON* * * | | | | DURING THE REMOVAL OF THERMOLAG MATERIAL, A FIRE RESISTANT MATERIAL THAT | | WAS INSTALLED IN 1987 AT THREE MILE ISLAND TO MEET THE REQUIREMENT OF | | APPENDIX "R" TO 10 CFR 50, WORKERS OBSERVED THAT SEVERAL PORTIONS OF FIRE | | BARRIER IAXC-FB-05 LOCATED IN FIRE ZONE AB-FZ-04 IN THE THREE MILE ISLAND | | UNIT 1 AUXILIARY BUILDING DID NOT HAVE A REQUIRED FILLET OF TROWEL GRADE | | MATERIAL 330-1. THE THERMOLAG WAS BEING INSPECTED IN PREPARATION TO | | REPLACE IT WITH MECATISS. SPECIFICALLY, VISUAL OBSERVATION DETERMINED THAT | | TROWEL GRADE MIX WAS NOT APPLIED TO TWO (2) SEAMS WHERE THERMOLAG | | INSULATION ABUTS THE REACTOR BUILDING EXTERIOR WALL AND ONE (1) SEAM WHERE | | THERMOLAG INSULATION ABUTS AGAINST A REACTOR BUILDING PENETRATION THERMOLAG | | INSULATION BOX AT THE TIME OF INSTALLATION OF THE THERMOLAG IN 1987. IN | | ADDITION, THERMOLAG INSTALLED AROUND A UNISTRUT WAS OBSERVED TO CONTAIN | | KAOWOOL FILLER MATERIAL AND DID NOT HAVE TROWEL GRADE MIX APPLIED TO THE | | END SEAM. | | | | THE CONTROL ROOM WAS NOTIFIED AND A FIRE WATCH WAS POSTED IN ACCORDANCE | | WITH THREE MILE ISLAND ADMINISTRATIVE PROCEDURE 1038, THE SITE FIRE | | PROTECTION PROGRAM PROCEDURE. REPAIRS ARE BEING MADE TO THE NON-CONFORMING | | SEAMS. | | | | AT 1450 HOURS, THE THREE MILE ISLAND PLANT REVIEW GROUP CONCLUDED A REVIEW | | OF THE NON-CONFORMING CONDITION AND DETERMINED THAT THE CONDITION WAS | | IMMEDIATELY REPORTABLE TO THE NRC IN ACCORDANCE WITH 10 CFR | | 50.72(b)(1)(ii)(B) AS A CONDITION OUTSIDE THE DESIGN BASIS OF THE PLANT AND | | AS A SUPPLEMENT TO EARLIER SIMILAR NOTIFICATIONS IN EVENT REPORTS 34682, | | AUGUST 25, 1998; 34769, SEPTEMBER 14, 1998 AND 34853, SEPTEMBER 29, 1998. | | THE CONDITION WAS DETERMINED TO BE REPORTABLE BECAUSE THE FIRE BARRIER DID | | NOT CONFORM TO ITS DESIGN BASIS AND THERE WAS REASONABLE JUSTIFICATION THAT | | THE NON-CONFORMING CONDITION WAS NOT THE RESULT OF AGE-RELATED DEGRADATION | | BUT RATHER AN INCORRECT INSTALLATION. | | | | ALL OF THE EARLIER EVENT REPORTS REFERENCED ABOVE AND THIS EVENT ARE | | RELATED IN THAT THEY HAVE THE SAME GENERAL CAUSE, INADEQUATE INSTALLATION, | | AND THE SAME GENERAL CONSEQUENCES, A FIRE BARRIER BEING OUTSIDE ITS DESIGN | | BASIS. THEREFORE, IN ACCORDANCE WITH THE GUIDANCE PROVIDED IN NUREG 1022 | | REV 1, EVENTS 34769, 34853 AND THIS REPORT WILL BE REPORTED IN A SUPPLEMENT | | TO LER 98-011, THAT REPORTED EVENT 34682. IN ADDITION, THERE IS SOME | | POSSIBILITY THAT ADDITIONAL SIMILAR CONDITIONS MAY BE DISCOVERED DURING THE | | COMPLETION OF THE PROJECT IN WHICH THERMOLAG IS BEING REPLACED WITH | | MECATISS. SUBSEQUENT SIMILAR EVENTS WILL BE REPORTED TO THE NRC VIA THE ENS | | SYSTEM AND BE REPORTED IN THE SUPPLEMENT TO LER 98-011 AND AS SUPPLEMENTAL | | IMMEDIATE REPORTS IN THIS EVENT REPORT 34856. THE SUPPLEMENT WILL BE ISSUED | | WHEN THE MECATISS INSTALLATION HAS BEEN COMPLETED (APPROXIMATELY MARCH 31, | | 1999). R1DO (JOHN CARUSO) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS UPDATE BY THE LICENSEE. | | | | * * * UPDATE 1452EDT ON 10/7/98 FROM JOHN SCHORK TO S.SANDIN * * * | | | | At 1452 hours on October 7, 1998, J. Schork, TMI PRG Chairman informed Mr. | | Steve Sandin of the NRC Operations Center by telephone that the existence | | of a condition outside the design basis of the TMI-1 plant had been | | determined by the TMI Plant Review Group at 1423 hours of October 7, 1998. | | This report is being made as a supplement to Event Report 34856 made on | | September 30, 1998. | | | | During the inspection of Thermolag material, a fire resistant material that | | was installed in 1987 at TMI to meet the requirements of Appendix R to 10 | | CFR 50, workers observed that a portion of fire barrier ICCD-FB08 located | | in fire zone CB-FA-1 in the TMI-1 Control Building had an area, size | | approximately 3.5" long and 2" wide, on the radial bend armor cable circuit | | ED 5033 A where Thermolag was missing. This non-conforming condition | | appears to be an original construction deficiency. | | | | The control room was notified and the deficiency was documented in the site | | corrective action program (CAP T1998-0867). An hourly fire watch was | | instituted in accordance with the site fire protection program procedure. | | Repairs are being made to the non-conforming seams. | | | | At 1423 hours, the TMI Plant Review Group concluded a review of the | | non-conforming condition and determined that the condition was immediately | | reportable to the NRC in accordance with 10 CFR 50.72(b)(l)(ii) as a | | condition outside the design basis of the plant and as a supplement to | | earlier similar notifications in event reports 34682, August 25, 1998, | | 34769, September 14, 1998 and 34853, September 29, 1998, 34856, September | | 30, 1998. The condition was determined to be reportable because the fire | | barrier did not conform to its design basis and there was reasonable | | justification that the non--conforming condition was not the result of | | age-related degradation but rather an incorrect installation. | | | | All of the earlier event reports referenced above and this event are | | related in that they have the same general cause, inadequate installation, | | and the same general consequences, a fire barrier being outside its design | | basis. Therefore, in accordance with the guidance provided in NUREG 1022, | | Rev. 1, events 34769,34853, 34856 and this report will be reported in a | | supplement to LER 98-011, that reported event 34682. In addition, there is | | some possibility that additional similar conditions may be discovered | | during the completion of the project in which Thermolag is being replaced | | with Mecatiss. Subsequent similar events will be reported to the NRC via | | the ENS system and be reported in the supplement to LER 98-011 and as | | supplemental immediate reports to Event Report 34856. The supplement will | | be issued when the Mecatiss installation has been completed (approximately | | March 31, 1999). | | | | The licensee informed the NRC resident inspector. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34881 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NONE |NOTIFICATION DATE: 10/06/98 | | CITY: SEATTLE REGION: 4 |NOTIFICATION TIME: 21:50 [ET]| | COUNTY: STATE: WA |EVENT DATE: 02/20/98 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[PDT]| | DOCKET: |LAST UPDATE DATE: 10/07/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM STETKA RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: TERRY FRAZEE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT | | | | THE FOLLOWING REPORT (WA-98-010) WAS RECEIVED IN THE OPERATIONS CENTER VIA | | EMAIL FROM THE STATE OF WASHINGTON AT 0650 ON 10/7/98: | | | | "A patient received a 12 millicurie dose of I-131 from a Washington state | | licensee and was released in accordance with current regulations (and | | therefore the following event is not "chargeable" against the licensee). | | On the way home the patient became nauseous and vomited in the parking | | strip of a busy street in Seattle. The patient reported this to the | | licensee who determined that the patient's car had little to no | | contamination and that approximately half the dose had been vomited. The | | event was immediately reported to the state Radiation Control Program and | | due to local weather conditions (it was raining very heavily in the area) | | an on-site response was delayed to the next day. A state inspector was | | able to locate the spot on the pavement where the vomitus hit using a | | survey meter. However, with the exception of a very small spot of | | non-removable contamination, all the vomitus had been washed away and no | | other detectable contamination was found. The manager of the fast food | | chain restaurant was informed of the reason for the survey in front of | | her establishment and the response closed out." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34882 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NONE |NOTIFICATION DATE: 10/06/98 | | CITY: BREMERTON REGION: 4 |NOTIFICATION TIME: 20:03 [ET]| | COUNTY: STATE: WA |EVENT DATE: 09/11/98 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[PDT]| | DOCKET: |LAST UPDATE DATE: 10/07/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM STETKA RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: TERRY FRAZEE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT | | | | THE FOLLOWING REPORT (WA-98-033) WAS RECEIVED IN THE OPERATIONS CENTER VIA | | EMAIL FROM THE STATE OF WASHINGTON AT 0650 ON 10/7/98: | | | | "A patient received a 20 millicurie dose of I-131 from a Washington state | | licensee and was released in accordance with current regulations (and | | therefore the following event is not "chargeable" against the licensee). | | On the way home the patient became nauseous and vomited in the dirt at | | the street-side near a church school parking lot. The patient reported | | this to the licensee who went to the site and confirmed that | | approximately half the dose had been vomited into the dirt. The | | licensee roped off the area, consulted with the state Radiation Control | | Program and planned to clean up the site by digging up and double-bagging | | the contaminated dirt. The dirt is to be held for decay at the | | licensee's facility." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34883 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 10/07/98 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 12:10 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/07/98 | +------------------------------------------------+EVENT TIME: 10:20[CDT]| |NRC NOTIFIED BY: RUSS GODWIN |LAST UPDATE DATE: 10/07/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | |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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY SIRENS INOPERABLE. STATE & LOCAL OFFICIALS NOTIFIED. | | | | DURING PERFORMANCE OF THE MONTHLY EMERGENCY NOTIFICATION SYSTEM IT WAS | | DISCOVERED THAT ALL EIGHT EMERGENCY NOTIFICATION SIRENS LOCATED IN EAST | | BATON ROUGE PARISH FAILED TO SOUND. TROUBLESHOOTING IS IN PROGRESS AND | | REPAIRS WILL BE MADE AS SOON AS POSSIBLE. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSE. | | | | * * * UPDATE 1815EDT ON 10/7/98 FROM RUSS GODWIN TO S.SANDIN * * * | | | | THE FOLLOWING INFORMATION WAS RECEIVED AS AN UPDATE: | | | | "FOLLOW UP TESTING OF INDIVIDUAL SIRENS REVEALED THAT ONLY THREE OF THE | | EIGHT EAST BATON ROUGE PARISH SIRENS WERE NOT FUNCTIONAL. THESE THREE | | SIRENS HAVE BEEN REPAIRED. | | | | "THIS FOLLOW UP TESTING ALSO REVEALED THAT FIVE ADDITIONAL SIRENS LOCATED | | IN OTHER PARISHES WERE NOT FUNCTIONAL." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. NOTIFIED | | R4DO(STETKA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34884 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/07/98 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:26 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/07/98 | +------------------------------------------------+EVENT TIME: 11:50[EDT]| |NRC NOTIFIED BY: MICHELE SAVINO |LAST UPDATE DATE: 10/07/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES LINVILLE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 WILL PERFORM A TECH SPEC REQUIRED SHUTDOWN DUE TO A MISSED | | SURVEILLANCE ON THE FIRST STAGE TURBINE PRESSURE. | | | | "AT APPROXIMATELY 1000EDT ON 10/7/98, IT WAS DISCOVERED THAT QUARTERLY | | FUNCTIONAL TEST IDENTIFIED BY TECH SPEC TABLE 4.1.1 ITEM 24, TURBINE FIRST | | STAGE PRESSURE, EXCEEDED ITS FREQUENCY FOR PERFORMANCE INCLUDING ITS | | ALLOWABLE GRACE PERIOD. TECH SPEC 3.0.1 WAS ENTERED AT 1150EDT. UPON | | REVIEW IT WAS DETERMINED THAT THE MINIMUM ESF INSTRUMENTATION REQUIRED BY | | TECH SPEC 3.5.2 WAS NOT MET DUE TO EXCEEDING THE REQUIRED TESTING | | FREQUENCY." | | | | THE LAST FUNCTIONAL TEST ON THE FIRST STAGE TURBINE PRESSURE WAS PERFORMED | | ON 6/13/98. THE LICENSEE IS CURRENTLY PERFORMING A QUARTERLY FUNCTIONAL | | TEST AND ANTICIPATES COMPLETION WITHIN 4-5 HOURS. HOWEVER, PREPARATIONS | | ARE IN PROGRESS TO COMMENCE A UNIT SHUTDOWN WITHIN THE HOUR. | | | | THE LICENSEE INFORMED THE NRC REGION I OFFICE AND THE RESIDENT INSPECTOR. | | | | * * * UPDATE 1426EDT ON 10/07/98 FROM M. SAVINO TAKEN BY MACKINNON * * * | | | | TECHNICAL SPECIFICATION 3.0.1 WAS EXITED AT 1310EDT UPON IN HOUSE AGREEMENT | | THAT THE REQUIREMENTS OF TECHNICAL SPECIFICATION 3.5.2 WERE SUCCESSFULLY | | MET DUE TO THE TESTING THAT HAD BEEN PERFORMED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS UPDATE BY THE LICENSEE. | | NOTIFIED R1DO(JAMES LINVILLE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34885 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 10/07/98 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 15:13 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 10/07/98 | +------------------------------------------------+EVENT TIME: 12:44[CDT]| |NRC NOTIFIED BY: CAROL BARAJAS |LAST UPDATE DATE: 10/07/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS KOZAK RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 99 POWER OPERATION | 99 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 3 DECLARED ITS ISOLATION CONDENSER INOPERABLE DUE TO A POTENTIAL | | FAILURE OF A REACTOR COOLANT ISOLATION VALVE. | | | | "UNIT 3 ISOLATION CONDENSER WAS DECLARED INOPERABLE AT 1244CDT ON 10/7/98, | | DUE TO THE POTENTIAL FAILURE OF THE REACTOR OUTLET ISOLATION MOV 3-1301-2 | | TO ELECTRICALLY OPERATE ON AN AUTOMATIC ISOLATION SIGNAL. PER AN | | ENGINEERING EVALUATION, THE MOV 3-1301-2 MOTOR PINION GEAR AND/OR KEY IS | | LOOSE AND DUE TO THE BEVEL OF THE TEETH ON THE MOTOR PINION GEAR, THE GEAR | | WILL TEND TO WALK IN A DIRECTION WHICH COULD CAUSE THE GEAR TO FALL OFF OF | | THE MOTOR SHAFT DURING THE CLOSING STROKE OF THE VALVE. THEREFORE, THERE | | IS A HIGH PROBABILITY THAT THE VALVE COULD FAIL TO CLOSE AS REQUIRED WHEN | | CALLED UPON TO PERFORM ITS DESIGNED SAFETY FUNCTION. TECHNICAL | | SPECIFICATION 3.5.D (ISOLATION CONDENSER) WAS ENTERED WHICH PLACED THE UNIT | | IN A 14 DAY LCO. ALL OTHER ECCS SYSTEMS ARE OPERABLE. TECHNICAL | | SPECIFICATION 3.7.D (PRIMARY CONTAINMENT ISOLATION VALVES) WAS ENTERED AND | | AT 1314CDT AN IN LINE ISOLATION VALVE WAS CLOSED AND DE-ACTIVATED TO MEET | | SPECIFICATIONS. THE ISOLATION CONDENSER WAS TAKEN OUT OF SERVICE AND MOV | | 3-1301-2 REPAIRS ARE UNDERWAY." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34886 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 10/07/98 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 15:58 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 10/07/98 | +------------------------------------------------+EVENT TIME: 13:50[EDT]| |NRC NOTIFIED BY: JEFF GROFF |LAST UPDATE DATE: 10/07/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS KOZAK 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DETERMINED THAT 5 OF 15 SRVs HAD RELIEF SETPOINTS HIGHER THAN | | ALLOWED. | | | | "AT 1350EDT ON 10/7/98, FERMI DETERMINED THAT 5 OF 15 SAFETY RELIEF VALVE | | (SRV) PILOTS FAILED TO MEET THE ALLOWABLE LIFTING SETPOINTS. TECHNICAL | | SPECIFICATION 3.4.2.1 REQUIRES THE SAFETY FUNCTION OF 11 OF 15 SRVs TO BE | | OPERABLE WITH THE SPECIFIED TOLERANCE OF ñ3%. THROUGH TESTING, IT WAS | | DETERMINED THAT ONLY 10 OF 15 SRVs WERE OPERABLE. | | | | "THE FOLLOWING SRVs FAILED: | | | | SRV 'C' +4.5% | | SRV 'J' +9.3% | | SRV 'K' +15.7% | | SRV 'M' +6.6% | | SRV 'P' +3.2% | | | | "FERMI IS CURRENTLY IN MODE 5(REFUELING) IN REFUELING OUTAGE #6." | | | | THE ABOVE RESULTS WERE FURNISHED BY WYLIE LAB AND REPRESENT A 100% | | INSPECTION OF THE 15 SRVs. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 34887 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: VETERANS AFFAIRS HEALTH CARE SYSTEM |NOTIFICATION DATE: 10/07/98 | | CITY: PALO ALTO REGION: 4 |NOTIFICATION TIME: 18:20 [ET]| | COUNTY: SAN MATEO STATE: CA |EVENT DATE: 09/10/98 | |LICENSE#: 04-23242-01 AGREEMENT: Y |EVENT TIME: 00:00[PDT]| | DOCKET: |LAST UPDATE DATE: 10/07/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |TOM STETKA RDO | | |JOHN SURMEIER EO | +------------------------------------------------+STUART RUBIN IRD | |NRC NOTIFIED BY: JOHN HOLMES | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DETERMINED THAT A SULFUR-35 SOURCE USED IN RESEARCH WAS MISSING. | | | | ON 9/10/98, THE RSO WAS INFORMED THAT A 1mCi (NOMINAL) SULFUR-35 DATP | | SOURCE USED FOR RESEARCH DNA TAGGING WAS MISSING FROM THE RESTRICTED | | STORAGE AREA. THE SOURCE, MANUFACTURED BY DUPONT NEN LIFE SCIENCES LOT | | #734H9809, WAS A FROZEN LIQUID STORED IN A PLASTIC BAG. AN NRC INSPECTOR | | VISITING THE FACILITY WAS INFORMED OF THE MISSING MATERIAL ON 9/14/98. THE | | LICENSEE HAS CONDUCTED AN EXHAUSTIVE SEARCH OF THE FACILITY INCLUDING | | RADWASTE WITH NEGATIVE RESULTS. HOWEVER, AN ANONYMOUS CALLER LAST WEEK | | CONTACTED THE RSO STATING THAT THE SOURCE HAD BEEN DISCARDED. THE LAST | | MEASURED SOURCE STRENGTH WAS 1.37 mCi ON 9/3/98 AND THE LICENSEE DOES NOT | | BELIEVE THIS REPRESENTS A SIGNIFICANT HEALTH RISK BASED ON ACTIVITY OF 8mCi | | SULFUR-35 PER 1 ALI. | | | | HOO NOTE: 10CFR PART 20 APPENDIX C QUANTITY 100 MICROCURIES | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34888 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 10/07/98 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 22:32 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 10/07/98 | +------------------------------------------------+EVENT TIME: 18:25[CDT]| |NRC NOTIFIED BY: RODNEY NACOSTE |LAST UPDATE DATE: 10/07/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IDENTIFIED A PRIMARY CONTAINMENT VALVE WHICH FAILED ITS LOCAL LEAK | | RATE TEST. | | | | "3-CKV-070-0506 FAILED 3-SI-4.7.A.2.g-3/70 PRIMARY CONTAINMENT LOCAL LEAK | | RATE TEST REACTOR BUILDING CLOSED COOLING WATER: PENETRATIONS X-23 AND 24. | | THE CHECK VALVE ALLOWED A LEAKAGE OF 2491 SCFH. THE CHECK VALVE LEAKAGE | | EXCEEDED THE MAXIMUM ALLOWED CONTAINMENT LEAK RATE OF 655.9 SCFH. | | | | "THIS EVENT IS REPORTABLE AS A 4 HOUR ENS PHONE CALL PER | | 10CFR50.72(b)(2)(i) AS 'ANY EVENT FOUND WHILE THE REACTOR IS SHUTDOWN THAT, | | HAD IT BEEN FOUND WHILE THE REACTOR WAS IN OPERATION, WOULD HAVE RESULTED | | IN THE NUCLEAR POWER PLANT INCLUDING ITS PRINCIPAL SAFETY BARRIER, BEING | | SERIOUSLY DEGRADED OR BEING IN AN UNANALYZED CONDITION THAT SIGNIFICANTLY | | COMPROMISES PLANT SAFETY.' | | | | "THIS IS ALSO REPORTABLE PER 10CFR50.73(a)(2)(ii) AS A 30 DAY WRITTEN | | REPORT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34889 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 10/08/98 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 03:19 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 10/08/98 | +------------------------------------------------+EVENT TIME: 02:30[EDT]| |NRC NOTIFIED BY: STEVE MAREK |LAST UPDATE DATE: 10/08/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: ALERT +-----------------------------+ |10 CFR SECTION: |THOMAS KOZAK RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JACK STROSNIDER EO | | |BERNICE CARR FEMA | | |STUART RUBIN IRD | | |TIM MARTIN AEOD | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALERT DECLARED DUE TO FIRE IN EMERGENCY DIESEL GENERATOR CONTROL PANEL | | | | AT 0230 EDT ON 10/8/98, THE LICENSEE DECLARED AN ALERT IN ACCORDANCE WITH | | EMERGENCY ACTION LEVEL HA-2, "FIRE OR EXPLOSION AFFECTING OPERABILITY OF | | PLANT SAFETY SYSTEMS REQUIRED TO ESTABLISH OR MAINTAIN SAFE SHUTDOWN. | | DURING A 24-HOUR POST-MAINTENANCE RUN OF EMERGENCY DIESEL GENERATOR EDG-12, | | AN OPERATOR NOTICED HEAVY SMOKE COMING FROM THE EDG CONTROL PANEL. THE | | OPERATOR TRIPPED THE ENGINE, OPENED THE OUTPUT BREAKER AND EXITED THE | | BUILDING. THE OPERATOR REPORTED THE CONDITION TO THE MAIN CONTROL ROOM. | | SUBSEQUENTLY, A FIRE ALARM WAS RECEIVED IN THE MAIN CONTROL ROOM. PERSONNEL | | REENTERED THE BUILDING USING SELF-CONTAINED BREATHING APPARATUSES, AND | | OBSERVED THAT THE FIRE WAS EXTINGUISHED. NO AUTOMATIC FIRE SUPPRESSION | | SYSTEMS WERE ACTUATED. THE CONTROL PANEL WAS DEENERGIZED AS A PRECAUTION. | | | | THE PLANT IS CURRENTLY IN DAY 33 OF A REFUELING OUTAGE. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE 0423 FROM WITTSCHEN TAKEN BY STRANSKY * * * | | | | THE ALERT WAS TERMINATED AT 0350 EDT. BASED UPON VISUAL INSPECTION, DAMAGE | | APPEARS TO BE LIMITED TO THE LOCAL CONTROL PANEL. THE LICENSEE PLANS TO | | ASSESS THE AREA FOR ADDITIONAL DAMAGE. THE NRC SENIOR RESIDENT IS ONSITE | | AND HAS BEEN INFORMED BY THE LICENSEE. NOTIFIED R3DO (KOZAK), NRR EO | | (STROSNIDER), IRD (RUBIN), AEOD (MARTIN), OPA (BEECHER), OIP (UPSHAW), FEMA | | (CARR), DOE (TANNER), HHS (GRAY), EPA/NRC (TURMAN), USDA (BICKERTON), | | CANADA (PERAULT, JAMES). | +------------------------------------------------------------------------------+