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Three "Oops" in the operational health physics
I noticed that these were missed last week. I think we should be concerned
with the lack of regulatory oversight in operational and reactor heatlh
physics, because individuals are not adequately assessing the risks. Am I
correct, Mr. Lipton?
-- John
John Jacobus, MS
Certified Health Physicist
3050 Traymore Lane
Bowie, MD 20715-2024
jenday1@email.msn.com (H)
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/07/2001 - 09/10/2001
** EVENT NUMBERS **
38268 38269 38270 38271
+---------------------------------------------------------------------------
---+
|Power Reactor |Event Number: 38268
|
+---------------------------------------------------------------------------
---+
+---------------------------------------------------------------------------
---+
| FACILITY: COLUMBIA GENERATING STATIREGION: 4 |NOTIFICATION DATE:
09/07/2001|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME:
00:47[EDT]|
| RXTYPE: [2] GE-5 |EVENT DATE:
09/06/2001|
+------------------------------------------------+EVENT TIME:
17:38[PDT]|
| NRC NOTIFIED BY: WILLIAM BAKER |LAST UPDATE DATE:
09/07/2001|
| HQ OPS OFFICER: FANGIE JONES
+-----------------------------+
+------------------------------------------------+PERSON
ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |LINDA SMITH R4
|
|10 CFR SECTION: |
|
|AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION |
|
| |
|
| |
|
| |
|
+-----+----------+-------+--------+-----------------+--------+--------------
---+
|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
+---------------------------------------------------------------------------
---+
| REACTOR CORE ISOLATION COOLING SYSTEM MADE INOPERABLE
|
|
|
| "Columbia Generating Station Reactor Core Isolation Cooing (RCIC) system
has |
| been isolated and made inoperable per Technical Specification 3.5.3 and
|
| unavailable due to manual closure of the RCIC turbine trip valve. The
|
| manual closure of the RCIC turbine trip valve was required due to the loss
|
| of automatic trip capability of the turbine trip valve [due to a solenoid
|
| failure]. This loss of automatic trip capability under postulated
|
| conditions could cause a water hammer event significant enough to threaten
|
| primary containment.
|
|
|
| "The RCIC system is a single train system and is listed in plant
procedures |
| as an Engineered Safety Feature (ESF).
|
|
|
| "The RCIC system will function automatically or manually to inject water
|
| into the RPV if manually returned to service."
|
|
|
| The licensee notified the NRC Resident Inspector.
|
+---------------------------------------------------------------------------
---+
+---------------------------------------------------------------------------
---+
|Power Reactor |Event Number: 38269
|
+---------------------------------------------------------------------------
---+
+---------------------------------------------------------------------------
---+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE:
09/07/2001|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME:
03:30[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE:
09/07/2001|
+------------------------------------------------+EVENT TIME:
00:24[CDT]|
| NRC NOTIFIED BY: MICHAEL FITZPATRICK |LAST UPDATE DATE:
09/07/2001|
| HQ OPS OFFICER: FANGIE JONES
+-----------------------------+
+------------------------------------------------+PERSON
ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |MARK RING 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 M/R Y 72 Power Operation |0 Hot Shutdown
|
| |
|
+---------------------------------------------------------------------------
---+
EVENT TEXT
+---------------------------------------------------------------------------
---+
| MANUAL REACTOR SCRAM DUE TO 2 LOW PRESSURE HEATER STRINGS ISOLATING
|
|
|
| The following is taken from a facsimile report:
|
|
|
| This report is being made per 10CFR50.72(b)(2)(iv)(B) RPS actuation
(scram) |
| (4 hour notification for U-2).
|
|
|
| At 12:24 AM CDT, Friday 9/7/01, U-2 was manually scrammed. The initiating
|
| event was a loss of 2 of 3 Low Pressure Feedwater Heater Strings. A high
|
| level condition was initially received in the 21A Low Pressure Heater,
which |
| caused the Condensate System inlet and outlet isolation valves to the 2A
Low |
| Pressure Heater String to close. Subsequently, a high level condition was
|
| also received in the 21C Low Pressure Heater, which caused the Condensate
|
| System inlet and outlet isolation valves to the 2C Low Pressure Heater
|
| String to close. With a second Low Pressure Heater String isolated, Unit 2
|
| was manually scrammed in accordance with LaSalle Procedure LOA-HD-201,
|
| "Heater Drain System Trouble".
|
|
|
| All systems operated as designed. There were no ECCS actuations or Primary
|
| Containment isolations. The lowest Reactor level reached was minus 20
inches |
| (141 inches above the top of active fuel) and was recovered to normal
level |
| using feedwater. Reactor pressure responded normally. No Safety Relief
|
| Valves actuated. All Control Rods fully inserted.
|
|
|
| The NRC Resident Inspector has been notified.
|
|
|
| The cause of the Low Pressure Heater String loss is being investigated at
|
| this time.
|
+---------------------------------------------------------------------------
---+
+---------------------------------------------------------------------------
---+
|General Information or Other |Event Number: 38271
|
+---------------------------------------------------------------------------
---+
+---------------------------------------------------------------------------
---+
| REP ORG: NEW MEXICO RAD CONTROL PROGRAM |NOTIFICATION DATE:
09/07/2001|
|LICENSEE: WESTERN TECHNOLOGIES |NOTIFICATION TIME:
18:31[EDT]|
| CITY: CUBA REGION: 4 |EVENT DATE:
09/06/2001|
| COUNTY: STATE: NM |EVENT TIME:
11:00[MDT]|
|LICENSE#: DM 244-29 AGREEMENT: Y |LAST UPDATE DATE:
09/07/2001|
| DOCKET:
|+----------------------------+
| |PERSON
ORGANIZATION |
| |LINDA SMITH R4
|
| |M. WAYNE HODGES NMSS
|
+------------------------------------------------+
|
| NRC NOTIFIED BY: SHERRY MILLER |
|
| HQ OPS OFFICER: JOHN MacKINNON |
|
+------------------------------------------------+
|
|EMERGENCY CLASS: NON EMERGENCY |
|
|10 CFR SECTION: |
|
|NAGR AGREEMENT STATE |
|
| |
|
| |
|
| |
|
| |
|
+---------------------------------------------------------------------------
---+
EVENT TEXT
+---------------------------------------------------------------------------
---+
| MISSING TROXLER DENSITY GAUGE.
|
|
|
|
|
| Western Technologies, out of Albuquerque, accidentally left a 3430 Troxler
|
| moisture density gauge at mile marker 49 on US highway 550. The moisture
|
| density gauge was out of its transport case laying on the side of the
|
| highway when the it was left behind. The driver immediately, within an
hour, |
| returned to the location and discovered that the gauge was missing. State
|
| of New Mexico has recommended to the licensee that they offer a reward for
|
| the missing gauge.
|
+---------------------------------------------------------------------------
---+
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