Event Notification Report for January 28, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/27/2000 - 01/28/2000
** EVENT NUMBERS **
36552 36607 36621 36629 36630 36631 36632 36633 36634 36635 36636 36637
36638
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36552 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 12/30/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 21:45[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 12/30/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 11:30[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/27/2000|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |BRUCE BURGESS R3 |
| DOCKET: 0707001 |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC WALKER | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|OCBA 76.120(c)(2)(i) ACCID MT EQUIP FAILS | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NOTE: THIS EVENT IS A CONTINUATION OF EVENT #35790. (Refer the event |
| #36018 and event #36605 for similar events at Portsmouth.) |
| |
| At 1130 CST on 12/30/99, the Plant Shift Superintendent (PSS) was notified |
| that during walkdowns of the High Pressure Fire Water System in C-337, a |
| total of 13 corroded sprinkler heads were discovered in System B-2. The |
| system was declared inoperable and actions were taken as required by the |
| technical safety requirement. The PSS determined that an update to this |
| event report is required. |
| |
| The NRC Resident Inspector has been notified of this event. |
| |
| * * * UPDATE 2233EST ON 1/12/00 FROM ERIC WALKER TO S. SANDIN * * * |
| |
| At 0910 on 1/12/00 the Plant Shift Superintendent (PSS) was notified that |
| during walk downs of the High Pressure Fire Water (HPFW) systems in C-337, |
| two adjacent corroded heads were discovered on system B-10. Per Engineering |
| Notice C-822-99-047 Rev. 2, the criteria necessary for system operability |
| was not being met. The system was declared Inoperable and actions were taken |
| as required by the TSR. The PSS determined that an update to this event |
| report is required. |
| |
| It has been determined that this event is reportable under 10CFR76.120(c)(2) |
| as an event in which equipment is disabled or fails to function as |
| designed. |
| |
| The NRC Resident Inspector has been notified of this event. Notified |
| R3DO(Clayton) and NMSS(Haughney). |
| |
| |
| *** UPDATE ON 1/21/00 @ 2306 BY UNDERWOOD TO GOULD *** |
| |
| At 1100 on 1/21/00, the Plant Shift Superintendent (PSS) was notified that |
| during walk downs of the High Pressure Fire Water (HPFW) systems in C-337, |
| thirteen corroded heads were discovered on system D-3. This system was |
| previously inspected on 6/24/99. Also, at 1640 on 1/21/00, the PSS was |
| notified that during walk downs of the HPFW systems in C-331, three adjacent |
| corroded heads were discovered on system 12. This system was previously |
| inspected by Fire Services Personnel on 4/10/99. Per Engineering Notice |
| C-822-99-047 Rev. 2, the criteria necessary for system operability was not |
| being met. The systems were declared inoperable and actions were taken as |
| required by the TSR. The PSS determined that an update to this event report |
| is required. |
| |
| The NRC Resident Inspector has been notified of this event. |
| |
| Reg 3 RDO(Hills) was notified. |
| |
| * * * UPDATE 1549 1/27/2000 FROM WHITE TAKEN BY STRANSKY * * * |
| |
| "At 1500 on 1/26/00, the Plant Shift Superintendent (PSS) was notified that |
| during walk downs of the High Pressure Fire Water (HPFW) systems in C-337, |
| eight corroded heads were discovered on system D-12. This system was |
| previously inspected on 8/28/99. Per Engineering Notice C-822-99-047 Rev. 2, |
| the criteria necessary for system operability was not being met. The systems |
| were declared inoperable and actions were taken as required by the TSR. The |
| PSS determined that an update to this event report is required." |
| |
| The NRC resident inspector has been notified of this event. |
| |
| Notified R3DO (Phillips). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36607 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 01/18/2000|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 19:15[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/18/2000|
+------------------------------------------------+EVENT TIME: 18:02[CST]|
| NRC NOTIFIED BY: R. T. THORTON |LAST UPDATE DATE: 01/27/2000|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID HILLS R3 |
|10 CFR SECTION: |ROBERTA WARREN IAT |
|DDDD 73.71 UNSPECIFIED PARAGRAPH |JIM CREED IAT |
| |JIM BELANGER IAT |
| |DICK ROSANO IAT |
| |STEVE REYNOLDS R3 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Decommissioned |
|2 N N 0 Decommissioned |0 Decommissioned |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SECURITY REPORT |
| |
| UNSUBSTANTIATED BOMB THREAT. COMPENSATORY MEASURES TAKEN. LICENSEE |
| INFORMED THE LOCAL POLICE DEPARTMENT. |
| |
| * * * RETRACTION 1533 1/27/2000 FROM NOLDEN TAKEN BY STRANSKY * * * |
| |
| After review of NRC Regulatory Guide 5.62, the licensee has determined that |
| this event was not reportable. Notified R3DO (Phillips). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36621 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/25/2000|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 06:44[EST]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/25/2000|
+------------------------------------------------+EVENT TIME: 06:10[EST]|
| NRC NOTIFIED BY: CORNAX |LAST UPDATE DATE: 01/27/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN ROGGE R1 |
|10 CFR SECTION: | |
|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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N Y 99 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BROKEN WINDOW IN A HIGH ENERGY LINE BREAK DOOR PLACES THE PLANT IN AN |
| UNANALYZED CONDITION |
| |
| A broken window in a High Energy Line Break Door which is located between |
| the Main Feed Regulating Valve Room and the Auxiliary Boiler Feed Pump Room |
| places the plant in an unanalyzed condition. Maintenance is fabricating a |
| metal replacement part to cover the opening. The door is supposed to remain |
| closed at all times when the plant is above 350 degrees F. |
| |
| The NRC Resident Inspector will be notified of this event by the licensee. |
| |
| * * * RETRACTION 1259 1/27/2000 TAKEN BY STRANSKY * * * |
| |
| "Indian Point has performed an engineering evaluation of the broken window |
| in the High Energy Line Break door located between the Main Feed Regulating |
| Valve room and the Auxiliary Boiler Feed Pump room and determined that the |
| equipment in the Auxiliary Boiler Feed Pump room would have maintained its |
| environmental qualification and the plant would have remained in an analyzed |
| condition even if the window was entirely missing. Therefore, this event has |
| been retracted." |
| |
| The licensee will inform the NRC resident inspector of this retraction. |
| Notified R1DO (Rogge). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36629 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 01/27/2000|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 11:35[EST]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 01/27/2000|
+------------------------------------------------+EVENT TIME: 09:00[EST]|
| NRC NOTIFIED BY: BANDHAVER |LAST UPDATE DATE: 01/27/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION TO FLORIDA FISH AND WILDLIFE CONSERVATION COMMISSION |
| |
| A GREEN SEA TURTLE(AN ENDANGERED SPECIES) WAS FOUND IN THE INTAKE. THE |
| TURTLE WILL BE HELD FOR A DAY TO ENSURE ITS HEALTH AND THEN RELEASED IN |
| ACCORDANCE WITH THE FISH AND WILDLIFE CONSERVATION COMMISSION DIRECTIONS. |
| |
| THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36630 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 01/27/2000|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 12:09[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 01/26/2000|
+------------------------------------------------+EVENT TIME: 22:38[EST]|
| NRC NOTIFIED BY: MUSGROVE |LAST UPDATE DATE: 01/27/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|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
+------------------------------------------------------------------------------+
| FAILURE OF PRIMARY CONTAINMENT ISOLATION VALVE TO CLOSE ON A LOW REACTOR |
| PRESSURE SIGNAL. |
| |
| PRIMARY CONTAINMENT ISOLATION VALVE "1E51-F008" DID NOT CLOSE ON A LOW |
| REACTOR PRESSURE SIGNAL DUE TO INSTRUMENT "1E51-N685C" BEING INOPERABLE. |
| THE OTHER VALVE IN THIS LINE, VALVE "1E51-F007", DID CLOSE TO ISOLATE THE |
| PENETRATION. THE "1E51-F008" VALVE WAS CLOSED AS DIRECTED BY THE SHUTDOWN |
| PROCEDURE "34G0-OPS-013-1S". THIS EVENT IS BEING INVESTIGATED TO DETERMINE |
| THE ROOT CAUSE. THE REPORTABILITY OF THE EVENT WAS NOT DETERMINED AT THE |
| TIME OF THE OCCURRENCE. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED. |
| |
| [HOO NOTE: SEE RELATED EN 36625.] |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36631 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/27/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:12[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/26/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:45[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/27/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |MONTE PHILLIPS R3 |
| DOCKET: 0707002 | NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MCCLEERY | |
| HQ OPS OFFICER: CHAUNCEY GOULD | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24 HOUR 91-01 BULLETIN RESPONSE |
| |
| AT APPROXIMATELY 1445 HRS @ 1/26/00, ELEVEN (11) BAGS WITH MISCELLANEOUS |
| CONTENTS WERE DISCOVERED IN THE X-103 HEALTH PHYSICS SOURCE VAULT. THREE |
| (3) OF THE ELEVEN ITEMS CONTAINED GREATER THAN 1% U-235 WITH THE HIGHEST |
| ASSAY BEING 52.1 %. THE TOTAL GRAM CONTENT OF ALL THREE ITEMS INCLUDING |
| ERROR IS 158.5 g U-235 FOR 52% ASSAY (MOST LIMITING). ALL ELEVEN ITEMS |
| WERE PLACED INTO TWO (2) APPROVED CONTAINERS WHICH WERE MOVED TO AN APPROVED |
| STORAGE FACILITY. |
| |
| |
| THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT. |
| |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED AND THE DOE REPRESENTATIVE WILL BE |
| NOTIFIED |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36632 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 01/27/2000|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 15:06[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/27/2000|
+------------------------------------------------+EVENT TIME: 11:22[CST]|
| NRC NOTIFIED BY: FRED SCHIZAS |LAST UPDATE DATE: 01/27/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GAIL GOOD R4 |
|10 CFR SECTION: | |
|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 Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR WATER CLEANUP ISOLATION WHILE PLACING SYSTEM IN SERVICE |
| |
| "During initial repressurization of the reactor water cleanup system (RWCU) |
| after the maintenance outage, the control room received channel 'A' and 'B' |
| RWCU high flow alarm (<=191% of rated flow) and subsequent Group 3 isolation |
| (closure of RWCU-MOV-M015 and RWCU-MOV-M018 inboard / outboard primary |
| containment isolation valves). This actuation occurred while the operator |
| was throttling open RWCU-M018. |
| |
| The Group 3 was verified per G.O.P. 2.1.22 (Recovery From Group Isolations) |
| and following recovery, system flow was restored." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36633 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/27/2000|
| UNIT: [] [2] [] STATE: CT |NOTIFICATION TIME: 15:10[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/27/2000|
+------------------------------------------------+EVENT TIME: 14:57[EST]|
| NRC NOTIFIED BY: STEVE BAKER |LAST UPDATE DATE: 01/27/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN ROGGE R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 M/R Y 100 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DUE TO SECONDARY SYSTEM TRANSIENT |
| |
| Operators manually tripped the unit from 100% power due to decreasing steam |
| generator water levels caused by a decrease in feedwater flow. Feedwater |
| flow decreased due to a transient in a feedwater heater string. All control |
| rods inserted following the trip. Operators also manually initiated the |
| auxiliary feedwater system to restore steam generator water levels (a |
| confirmatory automatic initiation signal was received). The unit is |
| currently stable in Hot Standby. All systems functioned as expected. |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36634 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 01/27/2000|
| UNIT: [] [2] [] STATE: VA |NOTIFICATION TIME: 15:38[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/27/2000|
+------------------------------------------------+EVENT TIME: 12:01[EST]|
| NRC NOTIFIED BY: DARLENE BROCK |LAST UPDATE DATE: 01/27/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN R2 |
|10 CFR SECTION: | |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| EXCESSIVE LEAKAGE THROUGH CONTAINMENT ISOLATION VALVE |
| |
| "On 1/27/00 at 1201 hours, as-found 10CFR50 Appendix J Type C leakage |
| testing of the outside containment trip valve 2-DA-TV-200B was determined to |
| be greater than 0.6 La. Leakage was determined to be approximately 182 scfh |
| versus total minimum pathway leakage acceptance criteria of 180 scfh. |
| |
| "On 1/25/00 the inside containment trip valve 2-DA-TV-200A for the same |
| penetration was replaced due to an unsatisfactory 1ST stroke time. Removal |
| and installation of the valve was less than one hour in duration. Following |
| replacement of the valve, Type C leakage was determined to be satisfactory |
| for 2-DA-TV-200A, however, excessive leakage was suspected for the outside |
| trip valve 2-DA-TV-200B. |
| |
| "By testing conducted on 1/27/00, it was confirmed that during the timeframe |
| of 2-DA-TV-200A replacement, a condition which alone could have prevented |
| the fulfillment of the safety function needed to control the release of |
| radioactive material existed. |
| |
| "Currently containment integrity is being maintained by closure and |
| deactivation of 2-DA-TV-200A in accordance with the station Technical |
| Specification. Following replacement of 2-DA-TV-200A on 1/25/00, Type C |
| testing was performed with satisfactory results (less than 1 scfh). |
| Currently total minimum pathway leakage is approximately 3 scfh. |
| |
| This report is being made pursuant 10CFR50.72(b)(2)(iii)." |
| |
| The licensee has informed the NRC resident inspector of this event. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 36635 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: USAF RADIOISOTOPE COMMITTEE |NOTIFICATION DATE: 01/27/2000|
|LICENSEE: USAF RADIOISOTOPE COMMITTEE |NOTIFICATION TIME: 16:51[EST]|
| CITY: KEESLER AFB REGION: 4 |EVENT DATE: 01/27/2000|
| COUNTY: STATE: LA |EVENT TIME: 15:00[CST]|
|LICENSE#: 42-23539-AF AGREEMENT: Y |LAST UPDATE DATE: 01/27/2000|
| DOCKET: 03028641 |+----------------------------+
| |PERSON ORGANIZATION |
| |GAIL GOOD R4 |
| |LARRY CAMPER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MAJ. HICKS | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MISSING CALIBRATION SOURCE |
| |
| On 1/26/00, the Keesler AFB Radiation Safety Officer (RSO) was unable to |
| locate a 1.37 �Ci Pu-239 calibration source during a routine inventory of |
| Wolfe Hall. During the subsequent investigation, the Wolfe Hall RSO reported |
| that the source was to have been transferred to Kelly AFB in Texas, but it |
| had inadvertently been shipped to McLellan AFB in California. However, the |
| McLellan AFB transportation office has no record of receiving the source. |
| The Keesler AFB RSO will continue to attempt to locate the source. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36636 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 01/27/2000|
| UNIT: [1] [2] [] STATE: TX |NOTIFICATION TIME: 17:12[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/27/2000|
+------------------------------------------------+EVENT TIME: 12:50[CST]|
| NRC NOTIFIED BY: PAUL COX |LAST UPDATE DATE: 01/27/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GAIL GOOD R4 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION DUE TO OIL SHEEN |
| |
| The licensee notified the Texas Natural Resource Conservation Commission and |
| the US DOT National Response Center regarding the appearance of an oil sheen |
| near the circulating water discharge. The licensee believes that the oil is |
| residue from recent paving activities that has been washed out due to heavy |
| rains. The licensee has deployed absorbent materials to control the spill. |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36637 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 01/27/2000|
| UNIT: [] [2] [3] STATE: CA |NOTIFICATION TIME: 19:13[EST]|
| RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 01/27/2000|
+------------------------------------------------+EVENT TIME: 15:30[PST]|
| NRC NOTIFIED BY: A. BOLYEN |LAST UPDATE DATE: 01/27/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GAIL GOOD R4 |
|10 CFR SECTION: | |
|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 100 Power Operation |100 Power Operation |
|3 N Y 100 Power Operation |100 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNITS OUTSIDE OF DESIGN BASIS DUE TO WORDING OF UFSAR |
| |
| "This notification is for San Onofre Units 2 and 3 and is being made in |
| accordance with 10CFR50.72(b)(1)(ii)(B). |
| |
| "Southern California Edison was performing a review of plant drawings and |
| noticed a potential discrepancy between some circuit designs and the |
| specific wording used in the Updated Final Safety Analysis Report (UFSAR) to |
| describe the design for those circuits. Further investigation of the |
| affected components revealed that certain functions appear to not fully meet |
| the separation criteria of Regulatory Guide 1.75, 'Physical Independence of |
| Electrical Systems.' These circuits include relays for portions of some |
| Engineered Safety Features (e.g., boric acid makeup pumps and input voltage |
| to one of the four loss-of-voltage-signal circuits). The UFSAR for Units 2 |
| and 3 indicates these systems comply with IEEE-279, 1971, 'Criteria for |
| Protection Systems for Nuclear Power Generation Stations' which is |
| referenced by Regulatory Guide 1.75. Consequently, at 1530 PDT, SCE |
| concluded this condition was reportable in accordance with |
| 10CFR50.72(b)(1)(ii)(B) as a condition 'outside the design basis of the |
| plant.' |
| |
| "SCE has confirmed that the affected components remain capable of performing |
| their intended safety functions and, therefore, concludes there is no safety |
| significance to this occurrence. |
| |
| "At the time of this report. Unit 1 remains permanently shutdown, and Units |
| 2 and 3 are operating at about 100% power. SCE will notify the NRC resident |
| inspectors of this condition and provide them with a copy of this report." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36638 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 01/28/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 05:14[EST]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 01/28/2000|
+------------------------------------------------+EVENT TIME: 02:40[CST]|
| NRC NOTIFIED BY: DARYL CLARK |LAST UPDATE DATE: 01/28/2000|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MONTE PHILLIPS R3 |
|10 CFR SECTION: | |
|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
+------------------------------------------------------------------------------+
| BOTH EMERGENCY DIESEL GENERATORS INOPERABLE DURING CORE ALTERATIONS |
| |
| "On 1/28/00 at 0005 hrs. the U- 2 Emergency Diesel Generator was found to be |
| inoperable due to the diesel generator room vent fan selector switch being |
| selected to the alternate feed. The 1/2 Emergency Diesel Generator was |
| inoperable due to Division I electrical system refuel outage work. Core |
| alterations were in progress. |
| |
| "Per Tech Spec 3.9.B, one diesel generator must be operable in Mode 5, and |
| when handling irradiated fuel in the secondary containment. |
| |
| "The switch was aligned to the normal position and vent fan operation was |
| verified within approximately 15 minutes to restore the U-2 diesel generator |
| to an operable status. An internal investigation is commencing. Although |
| both the 1/2 and U-2 EDGs were inoperable, both diesels remained available |
| for operation. |
| |
| "This event is being reported as required by 10CFR50.72(b)(2)(iii)(D), an |
| event which alone could have prevented the fulfillment of a safety function |
| needed to mitigate the consequences of an accident." |
| |
| The licensee informed the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021