Event Notification Report for April 18, 2000| ML041890307 |
| Person / Time |
|---|
| Site: |
Fermi, Saint Lucie, Point Beach, Prairie Island  |
|---|
| Issue date: |
04/18/2004 |
|---|
| From: |
NRC/RGN-II |
|---|
| To: |
|
|---|
| References |
|---|
| 36858, 36897, 36898, 36900, 36901, 36902, 38699, FOIA/PA-2004-0243 |
| Download: ML041890307 (5) |
|
|
|---|
Category:Status Report
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NRC-14-0001, DTE Electric Company Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-02-27027 February 2014
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NRC 2013-0078, NextEra Energy Point Beach, Llc'S First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Numb2013-08-28028 August 2013
NextEra Energy Point Beach, Llc'S First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA
NRC 2013-0077, NextEra Energy Point Beach, Llc'S First Six Month Status Report in Response to March 12, 2012 Commission Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2013-08-28028 August 2013
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2023-03-30
[Table view] |
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\ S U.S. Nuclear Regulatory Commissionm Home WhoWeAre WhatWeDo0RNuclearReacaors NuclearMerlals Radioactive ll Facility Into ll Public I iI 111 Waste Finder iiInvolvement Home > Electronic Reading Room > Document Collections > Reports Associated With Events > Event Notification Reports >
Event Notification Report for April 18, 2000 U.S. Nuclear Regulatory Commission Operations Center.
Event Reports For 04/17/2000 - 04/18/2000
36858 36897 36898 36899 36900 36901 36902 0
l1llllll THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED l1lllll
+-_____________________________________________________________________________+
lPower Reactor lEvent Number: 36858 l
+______________________________________________________________________________+
+______________________________________________________________________________+
FACILITY: PRAIRIE ISLAND REGION: 3 INOTIFICATION DATE: 04/03/20001 UNIT: [11 [21 [] STATE: MN INOTIFICATION TIME: 10:43[EDT1I RXTYPE: [1] W-2-LP [2] W-2-LP IEVENT DATE: 04/03/20001
+------------------------------------------------+EVENT TIME: 08:45[CDT]I l NRC NOTIFIED BY: STEVE GHEEN ILAST UPDATE DATE: 04/17/20001 HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION I IEMERGENCY CLASS: N/A ITHOMAS KOZAK R3 I 110 CFR SECTION:
IAOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS IUNIT ISCRAM CODEIRX CRITIINIT PWRI INIT RX MODE ICURR PWRI CURR RX MODE I
+____+__________+_______+________+_________________+________+_________________+
l1 N Y 100 Power Operation 1100 Power Operation l 12 N Y 100 Power Operation 1100 Power Operation III EVENT TEXT
+______________________________________________________________________________+
I HIGH ENERGY LINE BREAK ANALYSES (HELB) REQUIRE DOORS IN AREAS CONTAINING l MAIN STEAM LINES NOT BE BLOCKED OR OBSTRUCTED
-*DOORS 155/177 OBSTRUCTED BY SCAFFOLDING CAUSING DOORS TO BE PARTIALLY l BLOCKED. DUE TO HELB CONSIDERATIONS, DOORS NEED TO BE ABLE TO SWING OPEN l FULLY. SCAFFOLDING WAS MOVED AT 0925 CDT.-
THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR.
l * *
- RETRACTED AT 1130 EDT ON 4/17/00 BY WILLIAM MATHER TO FANGIE JONES * *
' Northern States Power Company's Nuclear Analysis Department (NAD) completed l I calculations based on the doors being blocked and as a result of these l calculations is withdrawing the Event Notification 836858." The analysis l indicates that.there is no significant effect on peak pressure during the I analyzed event.
l The licensee notified the NRC Resident Inspector. The NRC Operations I l Officer notified the R3DO (Patrick Hiland).
0 http://www.nrc.gov/reading-rm/doc-collections/event-status/event/2000/200004 18en.html 06/23/2004
11%1%%-. A-V%111L LNUL111%,"Llmis IVA X-XIJI11 LU, J.VJU I ar, VI -,
+ ------------------------------------------------------------------------ +
lPower Reactor lEvent Number: 36897 l
+______________________________________________________________________________+
FACILITY: FERMI REGION: 3 INOTIFICATION DATE: 04/17/20001 l UNIT: [21 [I (] STATE: MI INOTIFICATION TIME: 04:57EEDTII l RXTYPE: [2] GE-4 IEVENT DATE: 04/17/20001
+------------------------------------------------+EVENT TIME: 02:51EEDT]l l NRC NOTIFIED BY: JEFF GROFF ILAST UPDATE DATE: 04/17/20001 HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION lEMERGENCY CLASS: N/A IPATRICK HILAND R3 l 110 CFR SECTION: l IAESF 50.72(b)(2)(ii) ESF ACTUATION IUNIT ISCRAM CODEIRX CRITIINIT PWRI INIT RX MODE ICURR PWRI CURR RX MODE I l2 N N 0 Refueling 10 Refueling I I I I EVENT TEXT l CLOSURE OF A RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING OUTBOARD ISOLATION VALVE RESULTING IN LOSS OF AN RHR PUMP AND SUBSEQUENT LOSS OF SHUTDOWN l I COOLING FOR 21 MINUTES I The following text is a portion of a facsimile received from the licensee: I l 'At 0251 on 04/17/00, the E1150-FOO8 'RHR Shutdown Cooling (SDC) Outboard l Isolation Valve' closed causing the RHR 'B' pump to trip due to loss of l suction flow path. At the time of the trip, the RHR 'B' pump was in l operation for [SDCI.'
I *(SDC] was restored at 0312. During the event, Unit 2 was in Mode 5 --
Refueling -- with the vessel cavity flooded up to greater than 20' 6' above l the vessel flange with the fuel pool gates removed. No temperature rise in l the vessel was noted during the time SDC was out of service. No core I alterations were in progress at the time.'
'*Prior to the closure of the E1150-FOO8 valve, [the] Division 2 core spray I system was being tagged out of service for [refueling] outage maintenance. I l Part of the tag-out was to remove fuses for the core spray AC/DC inverter.
I Upon removing power to the inverter, a reactor high pressure signal caused a trip system B, group 4 -- Shutdown Cooling/Head Spray Isolation, which l closes the E1150-F008 valve. After the isolation, the core spray AC/DC l inverter was returned to service, the E1150-FOO valve opened, and RHR 'B' l pump was placed back into [the] SDC mode.'
' This event is being reported under IOCFR50.72(b)(2)(ii), any event or condition that results in the manual or automatic actuation of any engineered safety feature.,
l The licensee notified the NRC resident inspector.
+______________________________________________________________________________+
0
+______________________________________________________________________________+
lHospital lEvent Number: 36898
+ _ __ _ _ __ _ _ __ _ _ __ _ _ __ _ _ __ _ __ _ _ _ _ __ _ _ _ __ _ _ _ __ _ _ _ __ _ _ _ __ _ _ _ __ _ _ _ __ _ _ _ __ _ _ _ __ _ _ _ __ +
+-______________________________________________________________________________
I REP ORG: COMMUNITY HOSPITAL OF LANCASTER INOTIFICATION DATE: 04/17/20001 ILICENSEE: COMMUNITY HOSPITAL OF LANCASTER INOTIFICATION TIME: 09:48[EDT]l l CITY: LANCASTER REGION: 1 IEVENT DATE: 04/16/20001 l COUNTY: LANCASTER STATE: PA IEVENT TIME: 14:30[EDT]l lLICENSEt: 37-12495-01 AGREEMENT: N ILAST UPDATE DATE: 04/17/20001 l DOCKET: +------------------------------
I IPERSON ORGANIZATION I IJOHN WHITE R1 I IBRIAN SMITH NMSS I
+------------------------------------------------+CHARLIE MILLER IRO l l NRC NOTIFIED BY: MARY FEKETE l HQ OPS OFFICER: LEIGH TROCINE http://www.nrc.gov/reading-rmldoc-collections/event-status/event/2000/200004l8en.html 06/23/2004
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+___________________________ -_____________________ I IEMERGENCY CLASS: N/A I I 110 CFR SECTION: I I IBAAA 20.1906(d) SURFACE CONT/ EXT RAD I I I I EVENT TEXT RECEIPT OF A PACKAGE WITH SURFACE CONTAMINATION GREATER THAN THE 2,000 DPM/100 cm2 LIMIT On 04/16/00, a package arrived from Syncore (a pharmacy located in Harrisburg, Pennsylvania), and calculations following a wipe test of the 2
package revealed surface contamination of 13,600 DPM/cm . This was discovered at 0230 on 04/16/00. The licensee reported that the package contained technetium-99m and that the licensee normally receives 50 mCi in each package. At the time of this event notification, the package had not been opened, and there was no report of a breach. The licensee quarantined the package in a storage area and notified Syncore at 0245 on 04/16/00.
The licensee reported that the contamination is more likely to be around 2
2,400 DPM/cm because the efficiency of the well counter is based on cesium and the isotope involved was identified to be technetium-99m.
(Call the NRC operations officer for a licensee contact telephone number.) I 0
+_____-_____________________________________.___________________________________
lGeneral Information or Other lEvent Number: 36899 l
+______________________________________________________________________________+
+------------------------------- ----- +------
I REP ORG: INTERNAT. RAD & INSPECT. SVCS. INC. INOTIFICATION DATE: 04/17/20001
[LICENSEE: INTERNAT. RAD & INSPECT. SVCS. INC INOTIFICATION TIME: 11:44[EDT]1 l CITY: CATOOSA REGION: 4 IEVENT DATE: 04/14/20001 l COUNTY: STATE: OK IEVENT TIME: 11:30[CDT]l ILICENSE#: 35-30246-01 AGREEMENT: N ILAST UPDATE DATE: 04/17/20001 l DOCKET: I+----------------------------+
I 1PERSON ORGANIZATION l l IDALE POWERS R4 l IBRIAN SMITH MNSS l
+_______________________________-- - ---_________+ I l NRC NOTIFIED BY: WIELAND l HQ OPS OFFICER: CHAUNCEY GOULD l
+_____________________---______________________+ I IEMERGENCY CLASS: N/A l l 110 CFR SECTION:
IIBBF 30.50(b)(2)(ii) EQUIP DISABLED/FAILS I
++
EVENT TEXT
+______________________________________________________________________________+
l SOURCE DISCONNECT ON CAMERA OWNED BY INTERNATIONAL RADIOGRAPHY & INSPECTION l I SERVICES INC.
A radiography camera being used for an inspection by International l Radiography & Inspection Services Inc. at the Matrix Fabrication Division l site in Catoosa, Ok. had a source disconnect while being cranked out. The l source, which contained 72 curies of Iridium-192, was manufactured by AEA l Technologies and mounted in a SPEC camera. During the time of the source l disconnect, the area around the camera was secured. The licensee RSO went l to the site, did a source recovery and returned the camera to their l l facility. There were no exposures >40 mrem. The licensee has packaged the l l equipment and will FedEx it to AEA Technologies for their analysis of the l l problem.
+-_____________________________________________________________________________+
0 http://www.nrc.gov/reading-rm/doc-collections/event-status/event/2000/20000418en.html 06/23/2004
AX\. XVL1atIIbtIVII I'4 ljV1L IVI a-1ll JLU, /OVUMj I a 'ut VI IPower Reactor jEvent Number: 36900 l
+______________________________________________________________________________+
+______________________________________________________________________________+
l FACILITY: SAINT LUCIE REGION: 2 INOTIFICATION DATE: 04/17/20001 l UNIT: [1] (2] C] STATE: FL INOTIFICATION TIME: 12:35[EDT]I l RXTYPE: [1] CE,12] CE IEVENT DATE: 04/16/20001
+------------------------------------------------+EVENT TIME: 12:00[EDTJJ l NRC NOTIFIED BY: STEVE MERRILL ILAST UPDATE DATE: 04/17/20001 HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION I lEMERGENCY CLASS: N/A ICHRIS CHRISTENSEN R2 I 110 CFR SECTION:
IAPRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION l
+_____+__________+_______+________+_________________+________+_________________+
IUNIT ISCRAM CODEIRX CRITlINIT PWRI INIT RX MODE ICURR PWRI CURR RX MODE I
+_____+__________+-______+______-_+_________________+_______-+_______-_________+
ll N Y 100 Power operation 1100 Power Operation 12 N Y 68 Power Operation 168 Power Operation I EVENT TEXT I OFFSITE NOTIFICATION REGARDING DISCOVERY OF SEA TURTLE IN PLANT INTAKE l l CANAL
' At approximately 12:00 on 4/16/00, a loggerhead sea turtle was recovered I l from the plant's intake canal. The turtle was alive, but in need of l rehabilitation, and was subsequently sent to a facility at Sea World. As l required by the plant's sea turtle permit, the Florida Department of Environmental Protection (DEP) was notified of the event. The notification l I of the DEP necessitates a four (4) hour phone call to the NRC.
'*The licensee recognizes that this notification is being made outside the allotted four (4) hour window. The root cause will be investigated through l I the Condition Report process.'
l The NRC resident inspector has been informed of this notification by the i licensee.
+______________________________________________________________________________+
jPower Reactor lEvent Number: 36901 l
+______________________________________________________________________________+
l FACILITY: BEAVER VALLEY REGION: 1 INOTIFICATION DATE: 04/17/20001 UNIT: (l] [1 1] STATE: PA INOTIFICATION TIME: 15:56(EDT]j l RXTYPE: Cl] W-3-LP,(2] W-3-LP 1EVENT DATE: 04/17/20001
+------------------------------------------------+EVENT TIME: 13:09[EDTJI l NRC NOTIFIED BY: TOM COTTER ILAST UPDATE DATE: 04/17120001 HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
4-------------------------------------------------PERSON ORGANIZATION I lEMERGENCY CLASS: N/A IJOHN WHITE R1 I 110 CFR SECTION:
IARPS 50.72(b)(2)(ii) RPS ACTUATION l JAESF 50.72(b)(2)(ii) ESF ACTUATION l
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IUNIT ISCRAM CODEIRX CRITlINIT PWRI INIT RX MODE ICURR PWRI CURR RX MODE I
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Il M/R Y 100 Power Operation 10 Hot Standby I II I II I EVENT TEXT I MANUAL REACTOR TRIP DUE TO LOSS OF CONDENSER VACUUM
' At 13:04 on 4/17/00, BVFS Unit I experienced a loss of the turbine auxiliary steam header pressure. The loss of auxiliary steam pressure resulted in a decrease in condenser vacuum, rapidly approaching the low-low l vacuum turbine trip setpoint. At 1309, the reactor was tripped manually. l http://www.nrc.gov/reading-rmldoc-collections/event-status/eventI2000/20000418en.html 06/23/2004
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l Steam Generator 1C feed valve FCV-IFW-498 was isolated during recovery due l l to minor leakby. Auxiliary Feedwater and all other equipment responded as l expected. The initial problem was caused by a failure of the auxiliary steam l l supply pressure control valve air diaphragm packing. This valve is air to l l open and spring operated to close. Air pressure was lost through the failed l I packing causing the valve to fail in the closed position. Auxiliary steam was restored during plant stabilization. The plant is in Hot Standby and all l systems are functioning properly. Heat removal is via the normal condenser l I steam dump system.,
l The NRC resident inspector has been informed of this event by the licensee.
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lPower Reactor lEvent Number: 36902 l
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l FACILITY: POINT BEACH REGION: 3 INOTIFICATION DATE: 04/17/20001 l UNIT: [I (2] (I STATE: WI INOTIFICATION TIME: 16:021EDT]j l RXTYPE: [1] W-2-LP,[2] W-2-LP JEVENT DATE: 04/17/20001
+------------------------------------------------+EVENT TIME: 14:40ECDT3I l NRC NOTIFIED BY: JOHN SELL ILAST UPDATE DATE: 04/17/20001 HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION I IEMERGENCY CLASS: N/A IPATRICK HILAND R3 I 110 CFR SECTION: l IAOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS l IUNIT ISCRAM CODEIRX CRITIINIT PWRI INIT RX MODE ICURR PWRI CURR RX MODE I 12 N Y 100 Power Operation 1100 Power Operation l EVENT TEXT I SOURCE RANGE NEUTRON MONITOR COULD BE AFFECTED BY 10 CFR PART 50, APPENDIX R l l ISSUE l
- The cabling for Unit 2 source range monitor 2N-32 was found to be impacted l l by a postulated fire in either the CCW pump room or the Unit 2 MCC room in l l the 8' PAB. Per 10 CFR 50 Appendix R at least one nuclear instrument (2N-31, l I 2N-32 or 2N-40) must be available to monitor source range flux while l l shutting down the unit. [Monitor] 2N-32 is relied upon for a fire in [fire l l zone] FZ 142 and 166 due to cable losses on the 2N-31 and 2N-40 l l instruments. Loss of 2N-32 will cause a total loss of SR monitoring l capability which places the plant outside the Appendix R design basis.,
TThe NRC resident inspector will be informed of this notification by the l l licensee.
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0 http://www.nrc.gov/reading-rmldoc-collections/event-status/event/2000/200004 18en.html 06/23/2004