Event Notification Report for October 9, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/05/2001 - 10/09/2001
** EVENT NUMBERS **
37596 38352 38353 38355 38356 38357 38358 38359 38360 38361 38362
38363 38364 38365
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37596 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 12/14/2000|
| UNIT: [1] [] [] STATE: CT |NOTIFICATION TIME: 18:02[EST]|
| RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 12/14/2000|
+------------------------------------------------+EVENT TIME: 17:15[EST]|
| NRC NOTIFIED BY: DAVID DVORAK |LAST UPDATE DATE: 10/05/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN WHITE R1 |
|10 CFR SECTION: | |
|--APR50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
|KSNM 70.52(a) LOSS OF SNM/CRIT | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Decommissioned |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE LOCATION OF 2 FUEL PINS IN THE SPENT FUEL POOL IS UNKNOWN |
| |
| "As part of the ongoing decommissioning of Millstone Unit 1, a detailed |
| documentation of the fuel currently in the Unit 1 spent fuel pool is |
| underway. A detailed verification of spent fuel pool content records was |
| part of this effort. During this process, workers identified a discrepancy |
| in the paperwork relating to the location of two spent fuel pins that were |
| removed from a fuel assembly in October 1972. A search is underway; however, |
| these fuel pins have not yet been located among the 2,884 fuel assemblies |
| containing more than 140,000 fuel pins currently in the spent fuel pool. In |
| addition, workers are also searching pertinent records. |
| |
| "Due to the radiation levels of the fuel pins, if they were removed from the |
| spent fuel pool, the use of a shielded cask would have been required and the |
| shipment could have only been made to a licensed facility. Any other |
| movement of these pins from the site would have been immediately detected by |
| the site radiation monitoring system. Therefore, there is a high degree of |
| confidence that these pins are not in an unrestricted area and are under the |
| control of a licensed facility; either here in the spent fuel pool or |
| possibly at a licensed radioactive waste disposal site. As a result, we are |
| also confident that no overexposure of workers or members of the public has |
| resulted. An independent team with relevant expertise is on-site to assist |
| in an ongoing investigation to determine the location of the 2 fuel pins." |
| |
| The licensee notified NRC Region 1 (Todd Jackson) and the state of |
| Connecticut. The licensee intends notifying the NRC Resident Inspector. |
| |
| * * * UPDATE 1031EDT ON 10/5/01 FROM R. MALONEY TO S. SANDIN * * * |
| |
| The licensee is updating this report as follows to include the results of |
| their investigation: |
| |
| "DETAIL: |
| |
| "On October 1, 2001, Northeast Utilities provided its final report on the |
| Millstone Unit No. 1 fuel rod accountability project to DNC (Dominion |
| Nuclear Connecticut). This project was undertaken after it was determined |
| that 2 fuel pins from a Millstone Unit No. 1 spent fuel assembly could not |
| be accounted for. The NU project team conducted extensive inspections of the |
| Millstone Unit No. 1 spent fuel pool as well as comprehensive reviews of |
| material accountability and waste shipment records and interviews of |
| personnel historically involved with these activities. On the basis of this |
| report, DNC concludes it is unlikely that the pins are in the Millstone Unit |
| No. 1 fuel pool. The investigation into the disposition of the pins found no |
| evidence to indicate that the pins were diverted and concluded that the pins |
| were most likely intermingled with other contaminated material removed from |
| the Unit No. 1 spent fuel pool and shipped to a licensed low level waste |
| repository. The report concludes, based on a study performed by a reputable |
| expert, that the health and safety of the public has not been adversely |
| impacted by this condition. |
| |
| "This condition is reportable under 10CFR70.52(a) as a loss of special |
| nuclear material. |
| |
| "ACTIONS TAKEN: |
| |
| "A team of DNC personnel has reviewed the report and interviewed members of |
| the NU project team to obtain clarifications and additional information. A |
| separate root cause is being prepared by NU for this event. |
| |
| "RECOMMENDED ACTIONS: |
| |
| "Incorporate into the MP1 decommissioning plan, as necessary, any DNC |
| recommendations for additional future spent fuel pool inspections. |
| |
| "ADDITIONAL INFORMATION: |
| |
| "Dominion Nuclear Connecticut (the licensee) will be delivering copies of |
| the final report to NRC Headquarters and Region I offices for placement on |
| the docket today (10/05/01)." |
| |
| The licensee informed the NRC resident inspector. The NRC operations |
| officer notified the R1DO (Conte), NRR EO (Tappert), NMSS EO (Brown), IRO |
| (Wessman), NRR IAT (Skelton), NMSS IAT (Weber), NMSS (Essig), Region 1 |
| (Pangburn), OPA (Jasinski), and Liaison Team (Stauss). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38352 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 10/05/2001|
| UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 04:30[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/05/2001|
+------------------------------------------------+EVENT TIME: 00:26[EDT]|
| NRC NOTIFIED BY: J. A. WITTER |LAST UPDATE DATE: 10/05/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD CONTE R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(3)(v)(B) POT RHR INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNIT 2 ENTERED TECH SPEC 3.0.3 DUE TO TWO TRAINS OF SERVICE WATER DECLARED |
| INOPERABLE |
| |
| "At 0026 hrs on October 5, 2001, Beaver Valley Power Station Unit 2 |
| experienced a trip of the 'A' Train Service Water (SWS) Pump. 2SWS-P21 C was |
| operating on the 'A' SWS header when the pump tripped on Motor Ground Over |
| Current. Both A and B Train Emergency Service Water Pumps (SWE) auto started |
| as designed and Service Water header pressure returned to normal values. Due |
| to a piping class break, safety/non-safety, between the SWS and SWE systems, |
| the unit entered Technical Specification 3.0.3 due to two trains of Service |
| Water being Inoperable. The unit entered and completed the Abnormal |
| Operating Procedure for Loss of Service Water, and the Bravo Train of |
| Service Water was restored Operable when 2SWE-P21 B was secured and isolated |
| from the 'B' SWS header. 25W5-P21 B continued to operate normally during |
| this event. Technical Specification 3.0.3 was exited at 0037 hrs. The plant |
| is currently stable and operating at 100% power. Technical Specification |
| 3.7.4.1 for Service Water (72-hour action) is applicable, as the only |
| operating pump on the 'A' SWS header is 2SWE-P21A. The Alpha Service Water |
| Pump, 2SWS-P21 A is unavailable due to Intake Structure Bay cleaning. |
| Currently efforts are under way to recover the Intake Bay and restore |
| 2SWS-P21A Operable. It is expected that both trains of Service Water will be |
| Operable within 12 hours. The Non Safety Related Chiller units tripped due |
| to the SWS low pressure conditions, and were recovered shortly there after. |
| No additional failures or equipment challenges occurred as a result of this |
| event." |
| |
| The licensee informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 38353 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ABB INC. |NOTIFICATION DATE: 10/05/2001|
|LICENSEE: ABB INC. |NOTIFICATION TIME: 14:26[EDT]|
| CITY: REGION: |EVENT DATE: 10/05/2001|
| COUNTY: STATE: |EVENT TIME: [EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 10/05/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |VERN HODGE (FAX) NRR |
| |RICHARD CONTE R1 |
+------------------------------------------------+FRANK JAPE R2 |
| NRC NOTIFIED BY: RUSS GONNAM |DAVID HILLS R3 |
| HQ OPS OFFICER: FANGIE JONES |CLAUDE JOHNSON R4 |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT CONCERNING A CLASS 1E RELAY |
| |
| The following is the faxed report: |
| |
| Subject: Initial Notification of Potential Defect per 10 CFR Part 21 Type |
| CVE/CVE-1 Relays |
| |
| Provided By: ABB Inc., Substation Automation & Protection Division |
| |
| This letter is the initial notification of a deviation concerning our Class |
| 1E relay type CVE/CVE-1. The deviation concerns the difference between the |
| original zero period acceleration value and the recent zero period |
| acceleration value as reported to us by an independent dedicating entity. |
| |
| Details will be provided in our written notification forthcoming within the |
| next thirty days. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 38355 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: AVERA McKENNAN HOSPITAL |NOTIFICATION DATE: 10/05/2001|
|LICENSEE: AVERA McKENNAN HOSPITAL |NOTIFICATION TIME: 16:50[EDT]|
| CITY: FREEMAN REGION: 4 |EVENT DATE: 10/04/2001|
| COUNTY: STATE: SD |EVENT TIME: [MDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 10/05/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CLAUDE JOHNSON R4 |
| |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MARK EWING | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|IBAC 30.50(b)(1) UNPLANNED CONTAMINATION| |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SPILL OF TECHNETIUM IN PUBLIC AREA |
| |
| The mobile lab of Avera McKennan Hospital was on site at the Freeman |
| Hospital, Freeman, S.D. when a cracked vial containing 250 mCi of Technetium |
| leaked on to the floor of the kitchen. The area was secured and the only |
| exposure/contamination was the shoes of the medical technician transporting |
| the vial. A containment area was established and gross cleanup was |
| completed on 10/4/01. The area was checked again this morning and further |
| evaluation will be taken tomorrow, 10/6/01, after 8:00 PM, which will be |
| greater than ten half-lives. |
| |
| NRC Region 4 (Bob Brown) has been notified by the hospital chief technician. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38356 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 10/05/2001|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 17:11[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 10/05/2001|
+------------------------------------------------+EVENT TIME: [CDT]|
| NRC NOTIFIED BY: ED TIEDEMANN |LAST UPDATE DATE: 10/05/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID HILLS 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 100 Power Operation |99 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR REPORT IN ACCORDANCE WITH OPERATING LICENSE DUE TO POTENTIAL MAXIMUM |
| POWER LEVEL VIOLATION |
| |
| "This report is being made in accordance with Clinton Power Station Unit #1 |
| Operating License Condition #2.G as a potential violation of License |
| Condition #2.C(1), Maximum Power Level. |
| |
| "GE Report titled 'Impact of Steam Carryover Fraction on Process Computer |
| Heat Balance Calculations', September 2001, documents a non-conservative |
| assumption for the moisture carryover fraction used in the calculation of |
| core thermal power. The assumed carryover fraction of 0.1 % was discovered |
| to be potentially closer to zero and therefore non-conservative in later |
| model GE BWRs. |
| |
| "A review of Clinton Power Station Unit #1 moisture carryover test data |
| performed on May 21 2001 found a moisture carryover value of 0.0046% and on |
| October 4, 2001 found a moisture carryover value of 0.0020% inducing an |
| estimated bias of approximately 2.4 MWth. Based on this potential |
| non-conservatism on Unit #1 indicated Maximum Power Level shift average is |
| being administratively controlled 4 MWth below the licensed power level of |
| 2894 MWth. |
| |
| "Exelon staff is continuing to evaluate the effect of the moisture carryover |
| term in the heat balance calculation. The NRC resident has been notified." |
| |
| (Refer to event numbers 38330, 38337, 38340, 38344, 38445, 38347, 38349, and |
| 38357 for similar events at Fermi, Perry, Hope Creek, Grand Gulf, Columbia |
| Generating Station, Limerick 2, River Bend, and Limerick 1.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38357 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 10/05/2001|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 17:10[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/05/2001|
+------------------------------------------------+EVENT TIME: 11:15[EDT]|
| NRC NOTIFIED BY: PETER M. ORPHANOS |LAST UPDATE DATE: 10/05/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |RICHARD CONTE R1 |
|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 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 24-HOUR REPORT IN ACCORDANCE WITH OPERATING LICENSE DUE TO POTENTIAL MAXIMUM |
| POWER LEVEL VIOLATION |
| |
| The following text is a portion of a facsimile received from the licensee. |
| |
| "This report is being made in accordance with Limerick Generating Station |
| Unit 1 Operating License Condition 2.F as a potential violation of License |
| Condition 2.C(1), Maximum Power Level." |
| |
| "GE Report titled, 'Impact of Steam Carryover Fraction on Process Computer |
| Heat Balance Calculations,' September 2001, documents a non-conservative |
| assumption for the moisture carryover fraction used in the calculation of |
| core thermal power. The assumed carryover fraction of 0.1% was discovered |
| to be potentially closer to zero and therefore non-conservative in later |
| model GE BWRs." |
| |
| "A review of Limerick Unit 1 moisture carryover test data performed in |
| September of 1999 found a moisture carryover value of 0.1%. However, it is |
| believed that the results of the test may be more in line with the Limerick |
| Unit 2 data of 0.0277%. This results in an estimated bias of approximately |
| 2.8 MWth Based on this potential non-conservatism on Unit 1, an input |
| parameter of the Process Computer has been changed to eliminate this bias." |
| |
| 'Exelon staff is continuing to evaluate the effect of the moisture carryover |
| term in the heat balance calculation." |
| |
| The licensee plans to notify the NRC resident inspector. |
| |
| (Refer to event numbers 38330, 38337, 38340, 38344, 38445, 38347, 38349, and |
| 38356 for similar events at Fermi, Perry, Hope Creek, Grand Gulf, Columbia |
| Generating Station, Limerick 2, River Bend, and Clinton.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 38358 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: WA DIVISION OF RADIATION PROTECTION |NOTIFICATION DATE: 10/05/2001|
|LICENSEE: AMEC EARTH & ENVIRONMENT |NOTIFICATION TIME: 17:31[EDT]|
| CITY: UNIVERSITY PLACE REGION: 4 |EVENT DATE: 10/04/2001|
| COUNTY: STATE: WA |EVENT TIME: [PDT]|
|LICENSE#: WN-1093-1 AGREEMENT: Y |LAST UPDATE DATE: 10/05/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CLAUDE JOHNSON R4 |
| |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+JOHN DAVIDSON IAT |
| NRC NOTIFIED BY: TERRY FRAZEE | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE |
| |
| The following is the faxed report: |
| |
| City and state: Spokane, WA |
| License number: WN-l093-1 |
| Type of license: Portable Gauge |
| |
| Date of event: October 4, 2001 |
| Location of Event: University Place, WA |
| |
| ABSTRACT: A Troxler portable gauge was stolen from a pick-up parked at a |
| residence. An authorized user was returning home late from a job site and |
| knowing he had to go back early the next morning requested permission from |
| the licensee's Radiation Safety Officer to take the gauge home and secure it |
| there. The authorized user's home was closer than the licensee's storage |
| location. Permission was given and the gauge, a Troxler model 3440, serial |
| number 31199, was locked and chained in the bed of the pick-up. The |
| pick-up, which did not have a canopy, was parked in the residence's drive |
| way on the evening of October 4. The authorized user discovered early the |
| next morning that the chain had been cut and the gauge stolen. Neighbors |
| reported hearing noises about 11:45 PM that night. The theft was reported |
| to the local police, the licensee's corporate RSO and to the Department. A |
| reward is being offered for the gauge which contains 10 millicuries of |
| cesium 137 and 50 millicuries of americium 241/beryllium. |
| |
| What is the notification or reporting criteria involved? WAC 246-221-240 |
| (Reports of stolen, lost or missing radiation sources.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 38359 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: RESEARCH MEDICAL CENTER |NOTIFICATION DATE: 10/05/2001|
|LICENSEE: RESEARCH MEDICAL CENTER |NOTIFICATION TIME: 17:34[EDT]|
| CITY: KANSAS CITY REGION: 3 |EVENT DATE: 10/05/2001|
| COUNTY: JACKSON STATE: MO |EVENT TIME: 10:30[CDT]|
|LICENSE#: 24-18625-01 AGREEMENT: N |LAST UPDATE DATE: 10/05/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DAVID HILLS R3 |
| |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: STEVEN SLACK | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|LADM 35.33(a) MED MISADMINISTRATION | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION INVOLVING A MISSING IRIDIUM-192 SEED |
| |
| At 0830 CDT on 10/05/01, the licensee discovered that 1 of 71 iridium-192 |
| seeds was missing following a brachytherapy treatment involving both |
| cesium-137 tubes and iridium-192 ribbons. The licensee's investigation |
| revealed that the missing iridium-192 seed remained inside the patient. The |
| licensee determined that this event was reportable at 1030 CDT on 10/05/01. |
| |
| The patient was in surgery at the time of this event notification. As a |
| result, the total dose the patient has not yet been determined. The missing |
| iridium-192 seed had an activity of 0.89 millicuries. |
| |
| ***** UPDATE FROM STEVEN SLACK TO LEIGH TROCINE AT 1819 EDT ON 10/05/01 |
| ***** |
| |
| The missing iridium-129 seed was successfully recovered at 1645 CDT on |
| 10/05/01. |
| |
| The NRC operations officer notified the R3DO (David Hills) and NMSS EO |
| (Patricia Holahan). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38360 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 10/07/2001|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 03:13[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/07/2001|
+------------------------------------------------+EVENT TIME: [EDT]|
| NRC NOTIFIED BY: RONALD GREEN |LAST UPDATE DATE: 10/07/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |R1 IRC TEAM MANAGER R1 |
|10 CFR SECTION: | |
|AESF 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 M/R N 0 Hot Standby |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MANUAL REACTOR TRIP DURING TESTING |
| |
| "On 10/06/01, testing personnel and the Control Room crew were performing |
| 1BVT-1 .1.7, 'Rod Position Indication System Calibration Verification' and |
| 1BVT-1.1.1, 'Rod Drop Testing' in preparation for reactor startup after Unit |
| 1's 14th Refueling Outage. At 1959 hours, the Control Room operators |
| observed indications of 2 dropped control rods (rod position indication |
| reading zero steps and rod bottom lights on), and entered 1AOP-1.1.8 |
| (Abnormal Operating Procedure - Rod Inoperability). The Reactor Operator |
| opened the reactor trip breakers in accordance with the Abnormal Operating |
| Procedure and the Reactivity Management Plan that included reactivity limits |
| and recommended contingency actions. It was subsequently discovered that the |
| indications were caused by the test crew repositioning knife switches to |
| place the rod drop computer in service. The action and resulting indications |
| were not communicated to the Control Room crew. This event is being reported |
| under 10CFR 50.72(b)(3)(iv)(A), as a Specified System Actuation (RPS), |
| because a valid manual RPS signal (opening the reactor trip breakers from |
| the Control Room) was initiated which was not part of the pre-planned |
| testing in progress. All equipment functioned as expected, and no additional |
| failures or equipment challenges occurred as a result of this event. There |
| were no radiological releases associated with this event." |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38361 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 10/07/2001|
| UNIT: [1] [] [] STATE: MO |NOTIFICATION TIME: 06:11[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 10/07/2001|
+------------------------------------------------+EVENT TIME: 04:59[CDT]|
| NRC NOTIFIED BY: JOHN WEEKLEY |LAST UPDATE DATE: 10/07/2001|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |CLAUDE JOHNSON R4 |
|10 CFR SECTION: | |
|ACOM 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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| EMERGENCY OPERATIONS CENTER WITHOUT ELECTRICAL POWER FOR SCHEDULED |
| MAINTENANCE |
| |
| The licensee reported that the Emergency Operations Facility (EOF) will be |
| without power for approximately eight hours so that preplanned maintenance |
| can be performed. The NRC resident inspector has been informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38362 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 10/07/2001|
| UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 13:02[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/07/2001|
+------------------------------------------------+EVENT TIME: 09:50[EDT]|
| NRC NOTIFIED BY: STEVE CHERBA |LAST UPDATE DATE: 10/07/2001|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVID HILLS R3 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 A/R Y 8 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNEXPECTED REACTOR TRIP DURING PLANT STARTUP OPERATIONS |
| |
| ". . . . This event occurred at 0950 hours this morning (10-7-01). Currently |
| the Unit is in Mode 3 with all systems normal. At the time of the trip the |
| unit was at approximately 8 % power (by RCS AT indication, about 6 to 7 % on |
| Power Range Nuclear Instrumentation) in power ascension and was just |
| preparing to roll the main turbine. |
| |
| "RCS Tavg was noted to decrease below the normal 547 �F no-load post-trip |
| value to about 535 �F by the Reactor Operator monitoring the temperature. At |
| the time of the trip one main feedwater pump was supplying the Steam |
| Generators (SG), with low-flow feedwater pre-heating in service. Main |
| feedwater isolated on the trip with the SGs being supplied post trip by the |
| motor driven Auxiliary Feedwater (AFW) Pumps. The RCS cooldown was |
| attributed to the #4 SG AFW flow control valve not closing as expected on |
| high flow thus allowing too much flow to #4 SG, as well as steam that was |
| still being supplied to low flow feedwater preheating. Operator actions |
| taken in response to the cooldown were to close the main steam stop valves, |
| and review AFW valve positions so as to limit steam flow from, and feed flow |
| to, the SGs. These actions were completed by 0959 hours, and were sufficient |
| to maintain temperature control. RCS temperature shortly recovered to 547 �F |
| at about 1032 hours, 10-7-01. No other significant abnormalities were noted, |
| pressurizer pressure decreased in response to the temperature transient, and |
| the subsequent RCS shrink caused RCS letdown to isolate on low pressurizer |
| level. The plant is presently stable in Mode 3. No other RPS or SI setpoints |
| were exceeded due to the trip and subsequent temperature transient. All |
| other systems and equipment functioned normally. |
| |
| "The initiating RPS signal was a high Power Range Nuclear Instrument Rate |
| Trip on 2 out of 4 channels. Cause of this rate trip is not definitively |
| known at this time, rapid event teams to investigate and evaluate the trip |
| have been initiated. Suspected cause is a Rod Control System problem." |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 38363 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: STERIGENICS |NOTIFICATION DATE: 10/07/2001|
|LICENSEE: STERIGENICS |NOTIFICATION TIME: 17:38[EDT]|
| CITY: ROCKAWAY REGION: 1 |EVENT DATE: 10/06/2001|
| COUNTY: MORRIS STATE: NJ |EVENT TIME: 10:15[EDT]|
|LICENSE#: 29-30308-01 AGREEMENT: N |LAST UPDATE DATE: 10/07/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CLIFF ANDERSON/REG 1 IRC |
| |PATRICIA HOLAHAN NMSS |
+------------------------------------------------+RICHARD WESSMAN IRO |
| NRC NOTIFIED BY: STANLEY YAP | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|MAAA 36.83(a)(1) UNSHIELD STUCK SOURCE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| COMMERCIAL IRRADIATOR FACILITY REPORT REGARDING A SOURCE HANG UP |
| |
| Sterigenics is a panoramic, wet-source storage, commercial, irradiator |
| facility. At approximately 2215 EDT on 10/07/01, a 2.6-megacurie cobalt-60 |
| source got stuck in the unshielded position. The licensee attempted to lift |
| the source rack and had to release the ear out of the cylinder in the cell |
| to free it. The source rack was successfully returned it to its shielded |
| position within approximately 1 hour. There were no personnel radiation |
| exposures or injuries as a result of this event, and there was no source |
| leakage. |
| |
| The licensee is still investigating the cause of this event and has ceased |
| operations until engineering personnel can complete their evaluation. |
| |
| (Call the NRC operations officer for a site contact telephone number and |
| street address.) |
| |
| (Refer to event #38342 for a similar event at Sterigenics on 10/07/01.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38364 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 10/08/2001|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 08:33[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 10/08/2001|
+------------------------------------------------+EVENT TIME: 01:10[EDT]|
| NRC NOTIFIED BY: CHRIS SERATA |LAST UPDATE DATE: 10/08/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |R1 IRC TEAM MANAGER R1 |
|10 CFR SECTION: | |
|AINC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 95 Power Operation |95 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SECONDARY CONTAINMENT DECLARED INOPERABLE DURING SURVEILLANCE TESTING |
| |
| "During performance of the secondary containment drawdown test, reactor |
| building vacuum fluctuated between 0.49 and 0.50 inches wg. The acceptance |
| criterion for the test is greater than or equal to 0.50 inches wg vacuum. |
| Secondary Containment was therefore declared inoperable at 01:10. |
| Surveillance Requirement (SR) 4.6.5.1.c requires verification that the FRVS |
| will draw down the secondary containment to greater than or equal to 0.25 |
| inches wg vacuum. The test acceptance criterion ensures that vacuum |
| throughout the reactor building meets the SR acceptance criterion. Hope |
| Creek entered Technical Specification action statement 3.6.5.1 .a which |
| requires SECONDARY CONTAINMENT INTEGRITY to be restored within 4 hours or |
| the plant to be in HOT SHUTDOWN within the next 12 hours. |
| |
| "The FRVS reactor building pressure controller setpoint was found to be |
| incorrectly set. The controller was returned to the required setpoint and |
| reperformance of the test is in progress. |
| |
| "PSEG Nuclear is evaluating the test acceptance criterion and the |
| instrumentation used for the test." |
| |
| The licensee will inform the Lower Alloways Creek Township and the NRC |
| resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 38365 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 10/08/2001|
| UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 17:48[EDT]|
| RXTYPE: [3] B&W-L-LP |EVENT DATE: 10/08/2001|
+------------------------------------------------+EVENT TIME: 16:30[EDT]|
| NRC NOTIFIED BY: RICKY RAWLS |LAST UPDATE DATE: 10/08/2001|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JAY HENSON, REGION 2 IRC |
|10 CFR SECTION: | |
|ADEG 50.72(b)(3)(ii)(A) DEGRADED CONDITION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DISCOVERY OF A THROUGH-WALL LEAK AROUND ONE CONTROL ROD DRIVE MECHANISM |
| NOZZLE (REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAK) |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "On October 1, 2001, following shutdown for a scheduled refueling outage, |
| Crystal River Unit 3 (CR-3) performed a visual inspection of the Reactor |
| Vessel (RV) Control Rod Drive Mechanism (CRDM) nozzles per NRC Bulletin |
| 2001-01. The inspection revealed evidence of boric acid buildup around one |
| CRDM nozzle (#32). No other CRDM nozzle showed similar boron buildup. |
| After the RV head was removed and placed on the storage stand, additional |
| inspections were performed. At approximately 1610 on October 8, 2001, |
| Ultrasonic Test (UT) revealed a through-wall indication. This confirms that |
| the boron deposits around CRDM #32 indicate a Reactor Coolant System (RCS) |
| pressure boundary leak. This condition is consistent with industry |
| experience with Primary Water Stress Corrosion Cracking (PWSCC) in similar |
| components that have been evaluated as part of the NRC Generic Letter 97-01 |
| and NRC Bulletin 2001-01. Additional nozzles are being examined by UT in |
| accordance with CR-3's response to NRC Bulletin 2001-01. This condition did |
| not pose a significant safety risk during plant operation. CR-3 plans to |
| perform repairs during the current refueling outage. Since the condition |
| resulted in leakage through the RCS pressure boundary, it is being reported |
| as a non-emergency [8-hour] report in accordance with 10 CFR |
| 50.72(b)(3)(ii)(A) and 50.73(A)(2)(II)." |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021