Event Notification Report for March 22, 2001
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/21/2001 - 03/22/2001
** EVENT NUMBERS **
37698 37706 37853 37854 37855 37856
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37698 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 01/29/2001|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 05:36[EST]|
| RXTYPE: [3] CE |EVENT DATE: 01/28/2001|
+------------------------------------------------+EVENT TIME: 22:45[CST]|
| NRC NOTIFIED BY: PELLEGRIN |LAST UPDATE DATE: 03/21/2001|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DALE POWERS R4 |
|10 CFR SECTION: | |
|*INC 50.72(b)(3)(v)(C) POT UNCNTRL RAD REL | |
|*DEG 50.72(b)(3)(ii)(A) DEGRAD COND DURING OP | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| PRESSURIZER STEAM SPACE SAMPLE ISOLATION VALVES FAILED TO CLOSE |
| |
| At 2245 on 1/28/01 it was discovered that PSL-303 and PSL-304, Pressurizer |
| Steam Space Sample Inside and Outside Containment Isolation Valves would not |
| close when their respective control switches at OP-8 in the Control Room |
| were taken to the "Close" position. The valves had been open since 1455 |
| that same day to perform degas of the Pressurizer. The Nuclear Plant |
| Operator first took the switch for PSL-304 to the "Close" position and |
| observed that the valve continued to indicate "Open". He then took the |
| Switch for PSL-303 to the "Close" position, and observed that valve continue |
| to indicate "Open". Technical Specification 3.6.3 was entered and a Nuclear |
| Auxiliary Operator was dispatched to verify the position of PSL-304 locally. |
| PSL-304 was found to be in the open position and the on-shift chemistry |
| technician confirmed that there were still indications of flow through the |
| sample line. Another attempt to close PSL-304 was made using the switch on |
| CP-8 in the control room. The Nuclear Auxiliary Operator observed that the |
| valve moved approximately one quarter-inch in the closed direction. At |
| 2257 PSL-304 was closed using the manual gagging device. At 2310 PSL-304 |
| was de-energized to comply with the action requirements of Technical |
| Specification 3.6.3.b. At 0007 on 1/29/01, another attempt was made to |
| close PSL-303 using the control switch at OP-8. This attempt was successful. |
| The affected containment penetration is a one-half-inch line and is |
| currently isolated. They are investigating the cause. |
| |
| The NRC Resident Inspector was notified. |
| |
| * * * UPDATE AT 1717 ON 3/21/01, BY PIPKINS RECEIVED BY WEAVER * * * |
| |
| "This is an update to Event Number 37698, which was reported on 1/29/2001 at |
| 05:36 [EST]. After further evaluation by Entergy, the valve vendor |
| (Flowserve Engineering) was notified (March 16, 2001) concerning an apparent |
| defect in design related to inadequate internal valve clearances that |
| resulted in galling and subsequent binding of the subject valves (PSL-303 |
| and PSL-304). The vendor was asked to review the condition as a potential |
| 10 CFR Part 21 [report]. The vendor contacted Entergy today (3/21/01) and |
| indicated that, after review, they agree that the valve failure is a Part 21 |
| issue and agreed to issue the Part 21. The subject valves are 1/2 inch, |
| 2500 Ib, WKM model 70-18-9 DRTS cage-guided globe valves. In addition to |
| the original reporting criteria given in the call on 1/29/2001, the |
| condition is also reportable under 10 CFR50.72.(b)(3)(ii)(A) as a condition |
| involving principal safety barriers being seriously degraded. Entergy has |
| reviewed all of the safety-related applications of the subject valves at |
| Waterford 3 for other potential cases of common mode failure." |
| |
| The licensee notified the NRC resident inspector. The operations center |
| notified the R4DO (Pellet). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37706 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 01/31/2001|
| UNIT: [] [2] [] STATE: MI |NOTIFICATION TIME: 18:48[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/31/2001|
+------------------------------------------------+EVENT TIME: 11:45[EST]|
| NRC NOTIFIED BY: LEE JOHNSON |LAST UPDATE DATE: 03/21/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID HILLS R3 |
|10 CFR SECTION: | |
|*INC 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POTENTIAL INABILITY TO CONTROL A RADIOACTIVE RELEASE |
| |
| At 1145 on 1/31/01, the door to the auxiliary engineered safeguards suction |
| side vestibule in unit 2 was found stuck open. This bypasses the normal |
| flowpath for both trains of ESF fans and renders them inoperable. The plant |
| made an unrecognized entry into Technical Specification 3.0.3 until the door |
| could be closed, which occurred in approximately one minute. This eight |
| hour report is being made in accordance with 10 CFR 50.72 based on the |
| temporary inability to control a possible radioactive release. |
| |
| The licensee notified the NRC resident inspector. |
| |
| |
| * * * UPDATE AT 1543 ON 3/21/01, BY CHERBA RECEIVED BY WEAVER * * * |
| |
| The licensee has retracted this event based on the following analysis. |
| |
| "Subsequent evaluation concluded that if a postulated accident had occurred |
| while the door was open, control room doses would be less than 10CFR |
| Appendix A, GDC-19 limits and site boundary doses would remain within CNP's |
| accident analysis assumptions. This conclusion is based on an actual |
| measured total ECCS unfiltered leakrate of 0.02292 gpm, which is less than |
| the CNPs established limit of 0.2 gpm via the unit vent stack. Since the |
| total leakrate is less than 0.2 gpm, the AES system is not required to |
| filter the building effluent to maintain control room habitability during a |
| postulated accident. In addition, it was concluded that the ECCS pump and |
| heat exchanger rooms would not have experienced temperatures greater than |
| previously evaluated if a postulated accident had occurred while the door |
| was open. This was due primarily because of the low supply air temperature |
| (28 degrees Fahrenheit) and near freezing lake water temperature. |
| |
| "Based on the above, this event would not have impacted the radiation |
| removal capability of the AES ventilation system. As such, this |
| notification is being made to retract event 37706 made on January 31, |
| 2001." |
| |
| The licensee informed the NRC resident inspector. The operations center |
| notified the R3DO (Shear). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37853 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ARIZONA RADIATION REGULATORY AGENCY |NOTIFICATION DATE: 03/21/2001|
|LICENSEE: MAXIM TECHNOLOGIES, INC. |NOTIFICATION TIME: 12:59[EST]|
| CITY: CHANDLER REGION: 4 |EVENT DATE: 03/20/2001|
| COUNTY: STATE: AZ |EVENT TIME: 21:00[MST]|
|LICENSE#: AZ 07-168 AGREEMENT: Y |LAST UPDATE DATE: 03/21/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN PELLET R4 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: AUBREY GODWIN (fax) | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - STOLEN MOISTURE/DENSITY GAUGE |
| |
| "Between 7:00 and 9:00 PM, March 20, 2001, in a shopping area at 54th Street |
| and Ray Road a Troxler Model 3411B moisture/density gauge, SN 11906, was |
| stolen along with the truck containing the gauge. The truck is a 1993, white |
| Chevrolet S-10 pickup, AZ tag # 141CAE. This information was supplied by the |
| Radiation Safety Officer. The gauge contains an 8 millicurie cesium 137 |
| source and a 44 millicurie americium-241/beryllium source. The gauge was |
| locked to the pickup bed. Chandler Police Department is investigating this |
| matter, report # 01-24824. The LICENSEE is offering a $500.00 reward. The |
| Agency will be issuing a press release. |
| |
| "The LICENSEE and the Agency continue to investigate this event. |
| |
| "The states of Utah, California, Colorado, New Mexico, and Nevada together |
| with the U.S. NRC, the U.S. FBI and Mexico are being notified of this |
| event." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37854 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: USAF RADIOISOTOPE COMMITTEE |NOTIFICATION DATE: 03/21/2001|
|LICENSEE: USAF RADIOISOTOPE COMMITTEE |NOTIFICATION TIME: 17:54[EST]|
| CITY: SAN ANTONIO REGION: 4 |EVENT DATE: 01/01/2001|
| COUNTY: STATE: TX |EVENT TIME: [CST]|
|LICENSE#: 42-23539-01AF AGREEMENT: Y |LAST UPDATE DATE: 03/21/2001|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOHN PELLET R4 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DAVID PUGH | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOST AMERICIUM SOURCES |
| |
| Four chemical agent detectors were discovered on Kelly Air Force Base in San |
| Antonio, Texas. Each detector contains one or two Am-241 sources. Each |
| source has an activity of 160 �Ci. The origin of the detectors has not |
| been determined. The detectors had been mistakenly given to a subcontractor |
| about one year ago and then were returned to the Air Force a few months ago. |
| |
| |
| The licensee has discussed this event with Region IV. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37855 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 03/21/2001|
| UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 23:10[EST]|
| RXTYPE: [2] GE-4 |EVENT DATE: 03/21/2001|
+------------------------------------------------+EVENT TIME: 22:45[EST]|
| NRC NOTIFIED BY: PATRICK FALLON |LAST UPDATE DATE: 03/22/2001|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: ALE |GARY SHEAR R3 |
|10 CFR SECTION: |DAVID MATTHEWS NRR |
|*AEC 50.72(a) (1) (i) EMERGENCY DECLARED |NADER MAMISH IRO |
| |HENRY BAILEY RCT |
| |CHARLIE MILLER IRO |
| |YEATS DOE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| ALERT DECLARED - SMALL FIRE ON AN EMERGENCY DIESEL BEARING COVER |
| |
| The licensee declared an Alert when paint on the outboard generator bearing |
| cover of the #14 EDG caught fire. The fire was put out in less than one |
| minute with a portable CO2 extinguisher. The fire occurred at 2211 and the |
| Alert was declared retroactively at 2245. It was also terminated at 2245. |
| All other emergency equipment is operable. The plant continued to operate |
| at 100 percent power throughout the event. |
| |
| The licensee notified the NRC resident inspector, Monroe County, Wayne |
| County, the Province of Ontario and the State of Michigan. The Operations |
| Center made the following additional notifications. |
| |
| CANADA - PERREAULT, OIP - BRESKOVIC, OPA - BEECHER |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37856 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 03/22/2001|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 02:16[EST]|
| RXTYPE: [1] GE-3 |EVENT DATE: 03/21/2001|
+------------------------------------------------+EVENT TIME: 21:30[CST]|
| NRC NOTIFIED BY: DUSTIN WRIGHT |LAST UPDATE DATE: 03/22/2001|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SHEAR R3 |
|10 CFR SECTION: | |
|*UNA 50.72(b)(3)(ii)(B) UNANALYZED COND OP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| DRYWELL TO TORUS BYPASS LEAKAGE NOT REEVALUATED FOR POWER RERATE |
| |
| "An unanalyzed plant condition may exist due to Drywell to Torus bypass |
| leakage as defined in Tech Spec Bases 3.7.A was not reevaluated for power |
| rerate. The original evaluation determined that the maximum allowable |
| leakage capacity was 0.12 square feet. When power rerate was being |
| evaluated, General Electric assumed that Monticello was bound by a generic |
| evaluation for the drywell to torus allowable capacity of an 0.01 square |
| feet." |
| |
| Corrective action includes a reevaluation, as appropriate. The licensee |
| informed the NRC resident inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021