Event Notification Report for May 16, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/15/2001 - 05/16/2001
** EVENT NUMBERS **
37815 37816 37968 37989 37990 37991 37992 37993
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37815 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 03/08/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 13:04[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 03/05/2001|
+------------------------------------------------+EVENT TIME: 16:08[CST]|
| NRC NOTIFIED BY: PAT DECKER |LAST UPDATE DATE: 05/15/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|10 CFR SECTION: | |
|*UNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOW PRESSURE CORE SPRAY STRUCTURAL ANALYSIS DID NOT CONSIDER ALL POSSIBLE |
| FLOW CONDITIONS |
| |
| "On March 5, 2001, it was discovered that the structural analysis of |
| in-vessel Core Spray piping did not consider all applicable flow conditions. |
| A notification should have been made at that time because the effect of the |
| unanalyzed condition on degradation of plant safety was not considered with |
| respect to all plant operating conditions (i.e., the plant was shut down at |
| the time of discovery). Preliminary analysis results indicated that |
| previous analyses are bounding." |
| |
| This issue will be resolved before the next plant startup. |
| |
| The licensee will notify the NRC resident inspector. |
| |
| **** RETRACTION RECEIVED AT 1641 EDT ON 05/15/01 FROM PATRICK DECKER TO |
| LEIGH TROCINE **** |
| |
| The licensee is retracting this event notification. The following text is a |
| portion of a facsimile received from the licensee: |
| |
| "[...] On [03/08/01], we reported that structural analysis of the in-core |
| spray piping did not consider all the applicable flow conditions. Upon |
| re-evaluation, this is not reportable since: 1) this condition only |
| affected one train of core spray piping, and 2) the flaw condition believed |
| to have been overlooked was determined [analytically] to be bounded by |
| [existing] analyses." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R3DO (Parker). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37816 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 03/09/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 04:30[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 03/09/2001|
+------------------------------------------------+EVENT TIME: 01:30[CST]|
| NRC NOTIFIED BY: TIM ROGERS |LAST UPDATE DATE: 05/15/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN MADERA R3 |
|10 CFR SECTION: | |
|*SHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
|*ESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 A N 0 Refueling |0 Cold Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MODE CHANGE DUE TO LITERAL INTERPRETATION OF REQUIREMENTS |
| |
| "To meet compliance with literal interpretation of Tech Spec 3.7.A.5 and |
| 3.8.B.6, containment venting and purging using SBGT is required above 'Cold |
| Shutdown.' Plant is < 212�, all rods in BUT mode switch was in 'Refuel.' To |
| comply with Tech Specs, a Tech Spec shutdown with mode switch was performed. |
| All rods were already in but it wasn't a preplanned shutdown evolution. |
| Other similar 'Cold Shutdown' Tech Spec compliance issues are being looked |
| at." |
| |
| An automatic scram signal was generated when the mode switch was taken to |
| the 'Shutdown' position. Although all control rods were already inserted, |
| the licensee considers this action to be reportable as a valid safety system |
| actuation. The NRC resident inspector will be informed of this event by the |
| licensee. |
| |
| **** RETRACTION RECEIVED AT 1641 EDT ON 05/15/01 FROM PATRICK DECKER TO |
| LEIGH TROCINE **** |
| |
| The licensee is retracting this event notification. The following text is a |
| portion of a facsimile received from the licensee: |
| |
| "[...] On [03/09/01], we reported the failure to literally comply with |
| [Technical] Specification 3.7.A and 3.8.B.6. This event is being retracted |
| since 1) the requirement to use SBGT 'above' Cold Shutdown does not apply to |
| plant conditions where the plant is below the Cold Shutdown temperature of |
| 212 degrees F with the mode switch in 'refuel,' and 2) moving the mode |
| switch back to shutdown from 'refuel' was required to comply with a |
| prerequisite of an approved plant procedure. Therefore, this was part of a |
| preplanned sequence." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R3DO (Parker). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37968 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 05/06/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 06:02[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 05/06/2001|
+------------------------------------------------+EVENT TIME: 03:10[CDT]|
| NRC NOTIFIED BY: SCHMIDT |LAST UPDATE DATE: 05/15/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MELVYN LEACH R3 |
|10 CFR SECTION: | |
|*INA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 90 Power Operation |73 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MAIN TURBINE STOP VALVE FAILED TO CLOSE DURING TESTING |
| |
| The #4 main turbine stop valve failed to close during the performance of |
| turbine valve testing procedure. Failure of the turbine valve to close |
| affects the turbine stop valve closure scram function of both A&B reactor |
| protection trip systems. Reactor power is currently being reduced to less |
| than 45% power which is required when the minimum conditions for the turbine |
| stop valve closure scram function are not satisfied. The licensee believes |
| the cause of the problem is probably due to a bad solenoid valve. |
| |
| The NRC Resident Inspector will be notified. |
| |
| **** RETRACTION RECEIVED AT 1641 EDT ON 05/15/01 FROM PATRICK DECKER TO |
| LEIGH TROCINE **** |
| |
| The licensee is retracting this event notification. The following text is a |
| portion of a facsimile received from the licensee: |
| |
| "[...] On [05/06/01], we reported the failure to close of Main Turbine Stop |
| Valve #4 during routine testing. Subsequently, it was learned that the |
| failure affected the test circuit only and had no effect on the normal |
| operation of the stop valve. Therefore, this event is not reportable. The |
| test circuit failure has been corrected, and the Main Turbine Stop Valve #4 |
| retested successfully." |
| |
| The licensee notified the NRC resident inspector. The NRC operations |
| officer notified the R3DO (Parker). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37989 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: OTTWELL MALBY |NOTIFICATION DATE: 05/15/2001|
|LICENSEE: OTTWELL MALBY |NOTIFICATION TIME: 10:42[EDT]|
| CITY: TRAVERSE CITY REGION: 3 |EVENT DATE: 05/15/2001|
| COUNTY: STATE: MI |EVENT TIME: 10:30[EDT]|
|LICENSE#: 21-32235-01 AGREEMENT: N |LAST UPDATE DATE: 05/16/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SHEAR R3 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TOD CRAMER | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STRUCTURE FIRE INVOLVING NUCLEAR GAUGE |
| |
| The licensee reported that a fire is currently occurring at their field |
| office. A Troxler Model 3411 moisture/density gauge is currently stored in |
| the building. The sources are locked in their safe positions, and the gauge |
| is located in a storage locker. The licensee has notified local police and |
| fire departments regarding the presence of this device. |
| |
| ***** UPDATE RECEIVED AT 1515 ON 05/15/01 FROM TOD CRAMER TO LEIGH TROCINE |
| ***** |
| |
| The licensee is updating this event notification. The gauge was not damaged |
| in the fire. There was some water damage, and that area of the building was |
| reported to be underwater after the fire. The HAZMAT team obtained a |
| surface reading on the gauge, and the reading was 1 millirem per hour. The |
| gauge was intact, and there was no heat damage, melting, or physical damage. |
| The licensee plans to perform a wipe test and possibly repair the gauge. |
| |
| The licensee notified the Fire Department, HAZMAT, local/city police |
| agencies, and NRC region 3 office (Jim Hastings). The NRC operations |
| officer notified the R3DO (Parker) and NMSS EO (Cool). |
| |
| (Please call the NRC operations officer for a licensee contact telephone |
| number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37990 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: NC DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 05/15/2001|
|LICENSEE: S&ME |NOTIFICATION TIME: 14:56[EDT]|
| CITY: GREENSBORO REGION: 2 |EVENT DATE: 05/12/2001|
| COUNTY: STATE: NC |EVENT TIME: [EDT]|
|LICENSE#: 041-0922-1 AGREEMENT: Y |LAST UPDATE DATE: 05/15/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHARLES R. OGLE R2 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SHARN JEFFRIES | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT REGARDING A TROXLER MOISTURE DENSITY GAUGE |
| LOST/STOLEN FROM S&ME IN WINSTON SALEM, NORTH CAROLINA |
| |
| The following text is a portion of a facsimile received from the North |
| Carolina Department of Environment and Natural Resources, Division of |
| Radiation Protection: |
| |
| "SUBJECT: Incident 01-14" |
| |
| "Today, a North Carolina Portable Gauge Licensee (S&ME 041-0922-1 |
| Greensboro) reported a loss/theft of a Portable Moisture Density Gauge from |
| Winston Salem, NC, between the evening on Friday, May 11, 2001, and |
| Saturday, May 12, 2001. Local and State law enforcement agencies were |
| notified on Saturday, May 12, 2001. This Agency was notified by NC |
| Emergency Management of the incident at [1630] on Monday, May 14, 2001. The |
| Licensee reported the incident to this Agency [on] May 15, 2001." |
| |
| "The device that was lost/stolen is:" |
| |
| "Troxler 3411B Moisture Density Gauge SN 14682 |
| Cs-137 #50-3361 8 mCi |
| Am-241:Be #47-10037 40 mCi" |
| |
| (Call the NRC operations officer for a State contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37991 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: STORK TWIN CITY TESTING |NOTIFICATION DATE: 05/15/2001|
|LICENSEE: STORK TWIN CITY TESTING |NOTIFICATION TIME: 15:31[EDT]|
| CITY: ST. PAUL REGION: 3 |EVENT DATE: 05/08/2001|
| COUNTY: RAMSEY STATE: MN |EVENT TIME: 09:00[CDT]|
|LICENSE#: 22-01376-02 AGREEMENT: N |LAST UPDATE DATE: 05/15/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MICHAEL PARKER R3 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: PATRICK LIEBL | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| STUCK IRIDIUM-192 SOURCE AND FAILURE TO MAKE AN EVENT NOTIFICATION WITHIN 24 |
| HOURS |
| |
| On 05/05/01, an X-ray crew in Heron Lake, MN, was inspecting a flat bottom |
| tank using an Amertest-660A device containing 80 curies of iridium-192. At |
| 0900 CDT, during performance of an exposure, the stand that the guide tube |
| was connected to fell over and kinked the tube. As a result, the crew could |
| not initially retract the source. The crew subsequently followed procedures |
| and successfully retracted the source to its shielded position. There were |
| no overexposures as a result of this event. |
| |
| In preparation for submitting a 30-day letter, the licensee discovered |
| (today) that this event should have been reported as a 24-hour event |
| notification. |
| |
| (Call the NRC operations officer for a licensee contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37992 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 05/15/2001|
| UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 16:44[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 05/15/2001|
+------------------------------------------------+EVENT TIME: 16:08[EDT]|
| NRC NOTIFIED BY: BRUCE SHICK |LAST UPDATE DATE: 05/15/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN ROGGE R1 |
|10 CFR SECTION: | |
|*COM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 68 Power Operation |68 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MAJOR LOSS OF EMERGENCY PREPAREDNESS CAPABILITIES IN THE CALVERT COUNTY |
| AREA |
| |
| At 1608 on 05/15/01, the control room was notified that 40 of the 49 |
| [emergency] sirens failed to respond [during] the weekly silent test at |
| 1445. The apparent cause is currently believed to be a potential |
| transformer failure. Troubleshooting and repairs are in progress. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37993 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 05/16/2001|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 05:38[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/15/2001|
+------------------------------------------------+EVENT TIME: 07:00[CDT]|
| NRC NOTIFIED BY: BRYAN HERRING |LAST UPDATE DATE: 05/16/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MICHAEL PARKER R3 |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 98 Power Operation |98 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT MAY HAVE OPERATED ABOVE 100% POWER |
| |
| During power up-rate data verification, Byron Station identified that an |
| improper feedwater density factor and thermal expansion coefficient had been |
| used to calculate feedwater flow constants (referred to as AMAG constants) |
| on Units 1 and 2. The improper constants resulted in a non-conservative |
| determination of reactor power via the thermal power calorimetric |
| calculation. Thermal power was underestimated by 0.12 percent rated thermal |
| power. The improper AMAG constants have been utilized since AMAG was |
| implemented at Byron Station in May of 2000 (Unit 1 on 5/16/00 and Unit 2 on |
| 5/12/00). It is believed since May of 2000 either unit may have exceeded |
| 100 percent rated thermal power over an eight hour period based on the |
| non-conservative AMAG constants. There is no evidence that either unit ever |
| exceeded 102.0 percent rated thermal power. A formal review of past power |
| history for both units is in progress. The AMAG constants have been |
| corrected for Unit 2 and are in progress for Unit 1. Unit 1 is being |
| maintained at or below 99.88 percent rated thermal power until the AMAG |
| constants have been corrected. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021