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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  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35231       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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  |
| <= 73F.  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).                                                       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35236       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35237       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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).   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   35238       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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.                                                                    |
+------------------------------------------------------------------------------+