Event Notification Report for January 12, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/11/1999 - 01/12/1999
** EVENT NUMBERS **
35231 35236 35237 35238 35239 35240 35241 35242
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|Power Reactor |Event Number: 35231 |
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| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 01/08/1999|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 11:28[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/08/1999|
+------------------------------------------------+EVENT TIME: 10:35[EST]|
| NRC NOTIFIED BY: ? |LAST UPDATE DATE: 01/11/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM COOK R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| RHR SERVICE WATER PUMPS MAY NOT HAVE ADEQUATE NPSH |
| |
| A review of calculation VYC-990, R4 shows that inadequate NPSH exists for |
| RHR Service Water (RHRSW) pumps. VYC-990, R4 may not have conservatively |
| taken into account pump and system parameters, resulting in a condition of |
| being outside the design basis of the plant for the RHRSW system. |
| |
| The NRC resident inspector has been informed of this event by the licensee. |
| |
| * * * UPDATE 1557 1/11/99 FROM CREITZER TAKEN BY STRANSKY * * * |
| |
| The licensee submitted the following clarification of the initial report: |
| |
| "During a review of the NPSH calculations and input data for the RHRSW pumps |
| it was determined that potentially the calculation may not be conservative. |
| There is no operability concern for the RHRSW pumps at this time due to the |
| administrative restrictions the plant has put in place. (BMO 98-44) |
| Alternate Cooling System deep basin water temperature will be maintained at |
| <= 73�F. A Basis for Maintaining Operability (BMO) has been developed and |
| approved by plant management. |
| |
| "At the present time, the plant is operating in winter conditions and the |
| ambient conditions result in additional margin for NPSH. In addition, |
| Alternate Cooling System deep basin water temperature is monitored and |
| logged once per day. |
| |
| "Based on the above restrictions and conditions the available NPSH for the |
| RHRSW pumps is adequate, for the present and near term operability |
| conditions." |
| |
| NRC resident inspector has been informed of this event by the licensee. |
| Notified R1DO (Kelly). |
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|Other Nuclear Material |Event Number: 35236 |
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| REP ORG: USAF RADIOISOTOPE COMMITTEE |NOTIFICATION DATE: 01/11/1999|
|LICENSEE: USAF |NOTIFICATION TIME: 11:31[EST]|
| CITY: Washington D.C. REGION: 1 |EVENT DATE: 12/11/1998|
| COUNTY: STATE: DC |EVENT TIME: 08:00[EST]|
|LICENSE#: 42-23539-01AF AGREEMENT: N |LAST UPDATE DATE: 01/11/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BLAIR SPITZBERG R4 |
| |DONALD COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: Captain Coleman | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| Suspected loss of Radioactive material |
| |
| On 11 Dec 98 at 0800, Ramstein Air Force Base located in Germany notified |
| the Air Force Medical Operations Agency/Radiation Protection Division |
| located at Bolling Air Force, Washington, DC of the suspected loss of a |
| Niton XL, Model 309, Lead in Paint Spectrum Analyzer. The Niton contains a |
| sealed source with less than 50 millicuries of Cadmium-109. The item was |
| lost in shipment to the manufacturer. The Niton was shipped from Ramstein |
| to McGuire AFB, NJ, and then forwarded to the manufacturer on 12 Aug 98. |
| The subsequent search did not locate the Niton, however, bioenvironmental |
| engineers at McGuire AFB continue to research this suspected loss. No |
| suspected exposure is associated with this incident. An update on McGuire's |
| efforts will be provided to the NRC Region IV as soon as possible. |
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|Power Reactor |Event Number: 35237 |
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| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 01/11/1999|
| UNIT: [1] [2] [] STATE: AR |NOTIFICATION TIME: 11:56[EST]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 12/21/1998|
+------------------------------------------------+EVENT TIME: [CST]|
| NRC NOTIFIED BY: STEVE KAUFMANN |LAST UPDATE DATE: 01/11/1999|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BLAIR SPITZBERG R4 |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INFORMATION ON NEW METHOD TO DETERMINE ADULTERATION OF URINE SAMPLE |
| |
| The licensee determined that a pre-access urine sample was collected that |
| contained an improved type of commercially available adulterant. The sample |
| initially screened positive for but was later confirmed negative. Special |
| testing at a confirmatory laboratory determined the presence of an |
| adulterant. ANO Fitness for Duty has now taken action to detect this |
| adulterant during the collection process. |
| |
| Refer to HOO log for additional details. |
| |
| The licensee notified the NRC Resident Inspector and Region IV (Schaefer). |
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|Other Nuclear Material |Event Number: 35238 |
+------------------------------------------------------------------------------+
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| REP ORG: SPERRY-SUN |NOTIFICATION DATE: 01/11/1999|
|LICENSEE: SPERRY-SUN |NOTIFICATION TIME: 14:40[EST]|
| CITY: HOUSTON REGION: 4 |EVENT DATE: 12/16/1998|
| COUNTY: STATE: TX |EVENT TIME: [CST]|
|LICENSE#: 42-26844-01 AGREEMENT: Y |LAST UPDATE DATE: 01/11/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |BLAIR SPITZBERG R4 |
| |DONALD COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RICHARD ARSENAULT | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| RADIOACTIVE SOURCE LOST DURING SHIPMENT |
| |
| On 11/30/98, the licensee shipped an Amersham model CDC.CY13 oil well |
| logging source, containing a 2 Ci Cs-137 source (serial #2299GW), via |
| Federal Express. The package was picked up in Houston, TX, and was to be |
| transported to the north slope of Alaska. On 12/8/98, the licensee |
| contacted FedEx to determine the location of the package, as it had not been |
| received. On 12/15/98, Federal Express contacted the licensee and reported |
| that the package could not be found. Federal Express stated that the |
| package was tracked to a FedEx hub in Indianapolis, IN, but that no further |
| tracking information was available. On 12/16/98, the licensee contacted the |
| NRC Region IV office and reported the lost shipment. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35239 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 01/11/1999|
| UNIT: [1] [] [] STATE: LA |NOTIFICATION TIME: 16:56[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 01/11/1999|
+------------------------------------------------+EVENT TIME: 15:20[CST]|
| NRC NOTIFIED BY: RUSS GODWIN |LAST UPDATE DATE: 01/11/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BLAIR SPITZBERG R4 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| NOTIFICATION TO STATE DEPARTMENT OF ENVIRONMENTAL QUALITY |
| |
| "On January 11, 1999, RBS personnel made a report to the Louisiana |
| Department of Environmental Quality related to a potential defect in fuel |
| cladding. A previous report was made on September 21, 1998, and updated on |
| October 22, 1998. RBS personnel have continued to monitor plant conditions |
| after the first two had been suppressed. Chemistry sampling and power |
| suppression results indicate a probable third fuel failure. Indications |
| could be caused by a previously identified fuel failure. |
| |
| "The plant is operating at 100% power with radioactive releases well below |
| the limits of the Technical Requirements Manual and 10 CFR 20. Plant |
| personnel continue to implement site procedures to address the issue, and |
| take appropriate actions." |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35240 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 01/11/1999|
| UNIT: [1] [] [] STATE: CT |NOTIFICATION TIME: 17:56[EST]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 01/11/1999|
+------------------------------------------------+EVENT TIME: 17:00[EST]|
| NRC NOTIFIED BY: JON BOWER |LAST UPDATE DATE: 01/11/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GENE KELLY R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Decommissioned |0 Decommissioned |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| VENT STACK RADIATION MONITOR CALIBRATION PROCEDURE INADEQUATE |
| |
| The licensee has determined that the pressure transmitter compensation input |
| signal to the primary vent stack monitor (R-14A) was not recognized or used |
| in the calibration of the monitor. |
| |
| The following information was submitted by the licensee via facsimile: |
| |
| "The condition report [99-0011] has noted that the RM-14A monitor's output |
| signal is compensated based on the effects of the absolute pressure as |
| measured at the detector chamber by a pressure transmitter mounted on the |
| monitor skid. It has been determined that this pressure transmitter was |
| provided as part of the original design by the vendor (Victoreen). Also |
| noted is that the pressure transmitter Is not calibrated as part of the |
| radiation monitor's surveillance procedure and that no separate calibration |
| procedure exists for the pressure transmitter. |
| |
| "Radiation monitor RM-14A monitors the noble gas effluents being discharged |
| through the primary vent stack (which includes discharges from the Spent |
| Fuel Building). Plant modification number, PDCR 1550, approved on December |
| 11, 1995, replaced several radiation monitor channels, including RM-14A |
| (this PDCR is still open at present, with final installation being |
| completed). |
| |
| "PDCR 1550 noted in the bases of current design section that the replacement |
| RM-14A monitor Is non-QA and is not required during accident conditions |
| since it does not perform a safety related function. The replacement monitor |
| was purchased in accordance with CY specification SP-CY-EE-369. |
| |
| "The purpose of PDCR 1550 was to replace radiation monitors that were |
| obsolete or difficult to maintain. The design basis for RM-14A is to monitor |
| gaseous effluent r releases through the primary vent stack and provide |
| indication I alarms for the plant operator r the PDCR nor the purchase |
| specification noted the requirement for a pressure con compensated signal |
| for RM-14A. |
| |
| "Radiation monitor RM-14A was tested under PDCR 1550 and released for |
| operations on August 5,1996. As a condition of release this monitor was |
| calibrated and functionally tested by the surveillance test SUR 5.2-81.3 |
| (last performed on October 28, 1998).Since this surveillance test does not |
| include the calibration or functional check of the pressure transmitter, the |
| indicated radiation level may be inaccurate. This is interpreted as a missed |
| surveillance and inadequate functional testing of the RM-14A replacement |
| design. Therefore it is believed to be reportable under |
| 1OCFR5O.73(a)(2)(i)(B) as a condition prohibited by the plant's Technical |
| Specifications. |
| |
| "The Victoreen Technical Manual is a 2 volume set that provides |
| installation, operation and maintenance instructions as well as factory test |
| procedures and initial data. The organization of this information is |
| somewhat confusing regarding the use of or need for the pressure |
| transmitter. The system overview does not discuss this function at all, the |
| theory of operation section states that the signal is used to calculate the |
| radiation value 'when used,' and the section on 'optional circuit boards' |
| lists an analog input board that can be used for the pressure input signal. |
| |
| "SP-CY-EE.369 specified technical requirements and factory acceptance |
| testing for the radiation monitors purchased under PDCR 1550. CY personnel |
| were to witness (indeterminate if performed) factory calibration tests of |
| the monitors. Victoreen's factory test data sheet for the monitor's |
| electronic check had a hand written entry that the pressure transmitter |
| input was disabled during the test, this step is not documented in their |
| test procedure. |
| |
| "The PDCR and surveillance test procedure for RM-14A failed to recognize |
| that the pressure transmitter input signal was used to calculate a |
| compensated radiation value. This indicates an inadequate understanding of |
| system design and instrument calibration by plant personnel. Therefore it is |
| believed to be reportable under 10CFR5O.73(a)(2)(ii)(B) outside the design |
| basis of the plant." |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35241 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 01/11/1999|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 19:01[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/11/1999|
+------------------------------------------------+EVENT TIME: 16:41[EST]|
| NRC NOTIFIED BY: ERV PARKER |LAST UPDATE DATE: 01/11/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GENE KELLY R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NINF INFORMATION ONLY | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| RCIC SYSTEM DECLARED INOPERABLE |
| |
| The licensee manually closed the Reactor Core Isolation Cooling (RCIC) |
| outboard steam supply isolation valve in accordance with plant Technical |
| Specifications. At 1541, the Isolation Actuation Instrumentation System TS |
| was entered due to an apparent component power supply failure in the steam |
| leak detection isolation circuitry. The licensee is currently |
| troubleshooting the power supply problem with the steam leak detection |
| circuitry. With the RCIC outboard steam supply isolation valve closed, the |
| system is not capable of performing its intended function. The High |
| Pressure Coolant Injection (HPCI) system is currently operable. The NRC |
| resident inspector will be informed of this event by the licensee. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35242 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 01/11/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 20:27[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/11/1999|
+------------------------------------------------+EVENT TIME: 16:28[EST]|
| NRC NOTIFIED BY: DON KOSLOFF |LAST UPDATE DATE: 01/11/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM GAVULA R3 |
|10 CFR SECTION: | |
|ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| SAFETY RELATED RELAYS MAY NOT BE SEISMICALLY QUALIFIED |
| |
| "General Electric HFA safety related relays may be inoperable due to |
| inadequate seismic qualification. Several hundred relays are now being |
| evaluated to determine which ones need to be checked for qualification. The |
| HFA relays are supplied with normally open contacts. If contacts are changed |
| to normally closed, the contacts must be checked to verify contact |
| synchronization and wipe. There is no evidence that the verification has |
| been performed. Therefore all relays are considered suspect and all four |
| emergency diesel generators were declared inoperable at 1628 hours on |
| January 11, 1999. |
| |
| "Evaluation of this condition is continuing. An initial list of relays that |
| require checking is being compiled and action requests are being written to |
| perform the required checks. Both Units are currently in Mode 5." |
| |
| The NRC resident inspector will be informed of this notification by the |
| licensee. |
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