Event Notification Report for January 8, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/07/1999 - 01/08/1999
** EVENT NUMBERS **
35126 35218 35224 35225 35226 35227 35228
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35126 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 12/08/1998|
| UNIT: [1] [] [] STATE: VT |NOTIFICATION TIME: 21:09[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 12/08/1998|
+------------------------------------------------+EVENT TIME: 20:55[EST]|
| NRC NOTIFIED BY: MCCLUSKIE |LAST UPDATE DATE: 01/07/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN ROGGE R1 |
|10 CFR SECTION: | |
|AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| BOTH TRAINS OF STANDBY GAS TREATMENT DECLARED INOPERABLE. |
| |
| DURING PREPARATION OF DESIGN BASIS DOCUMENTATION (DBD) FOR THE STANDBY GAS |
| TREATMENT SYSTEM (SBGTS), A CONDITION WAS DISCOVERED WHICH COULD LEAD TO |
| DEGRADATION OF BOTH SBGTS TRAINS. |
| |
| A REVIEW OF THE SIZING OF THE SBGTS LOOP SEAL LINES INDICATED THAT, DURING |
| THE INITIAL STAGES OF A DESIGN BASIS ACCIDENT (DBA) WITH THE SBGTS INLET |
| NORMALLY ALIGNED TO THE TORUS TO MAINTAIN DRYWELL TO TORUS DIFFERENTIAL |
| PRESSURE, THE RESULTING TORUS PRESSURE INCREASE WOULD CAUSE AN OVERPRESSURE |
| CONDITION WHICH WOULD RESULT IN A PRESSURE, WITHIN THE UNITS, OF 1.8 PSIG. |
| ALTHOUGH, THIS PRESSURE IS WITHIN THE INTERNAL ALLOWABLE PRESSURE OF THE |
| UNITS THE EFFECT WOULD BE TO CAUSE A CLEARING OF THE EACH UNIT LOOP SEAL. |
| THE RESULTING FLOW THROUGH THE LOOP SEAL INTO THE UNIT WOULD BYPASS THE |
| MOISTURE SEPARATOR AND WOULD BE OF SUFFICIENT VELOCITY TO PREVENT |
| RE-ESTABLISHMENT OF THE LOOP SEAL BY DRAINS FROM THE MOISTURE SEPARATOR. |
| WITHOUT REFILL OF THE LOOP SEALS, THE WATER COLLECTED BY THE DEMISTER WILL |
| ACCUMULATE IN THE UNITS POTENTIALLY REDUCING THE EFFECTIVENESS OR FAILING |
| THE HEATER, THE HEPA FILTERS, AND THE CHARCOAL ADSORBERS. |
| |
| THIS CONDITION HAS BEEN EVALUATED AND A MODIFICATION TO THE LOOP SEAL VALVE |
| LINEUP WILL BE PERFORMED TO THROTTLE THE LOOP SEAL DRAIN VALVE TO ENSURE |
| THAT FLOW INTO THE UNIT, THROUGH THE LOOP SEAL DRAIN LINE, IS NOT OF |
| SUFFICIENT VELOCITY TO PREVENT REFILLING OF THE LOOP SEALS. THE EFFECT OF |
| THE BYPASS FLOW ON THE OPERATION OF THE UNITS HAS ALSO BEEN EVALUATED AND |
| FOUND TO BE OF INSUFFICIENT VOLUME TO EFFECT THE PROPER OPERATION OF THE |
| SBGTS HEATER, HEPA FILTERS, OR CHARCOAL ADSORBERS. |
| |
| THE LICENSEE IS IN TECHNICAL SPECIFICATION 3.7.C.2 (FOUR HOURS TO RESTORE |
| SECONDARY CONTAINMENT) AND TECHNICAL SPECIFICATION 3.7.B.4 (24 HOURS TO |
| RESTORE BOTH TRAINS OF SBGT WHICH ARE NOW INOPERABLE). THE LICENSEE WILL |
| NOTIFY THE STATE OF THIS EVENT. |
| |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. |
| |
| * * * RETRACTION 1046 1/7/99 FROM M. MAGNUSON TAKEN BY STRANSKY * * * |
| |
| The licensee is retracting this event notification. The following text was |
| submitted in support of the retraction: |
| |
| "Vermont Yankee Engineering has analyzed the particulars of this cited |
| condition. Vermont Yankee's conclusion is that the as-built seal |
| configuration will not preclude proper operation of the unit. |
| |
| "The demister-loop seal does not bypass the radioactive filtration elements |
| of the unit. Additional essential observations / conclusions include: |
| |
| "a) Contrary to the preliminary assessment, further evaluations, including |
| a preliminary calculation concluded that if there is significant moisture in |
| the process stream it will rapidly refill the loop seal (were it to be |
| voided by the pressure pulse described in the original report), and |
| |
| "b) If there is insufficient moisture available for a rapid refill, then |
| there is not sufficient moisture to challenge the charcoal filter element. |
| |
| "c) Therefore, the system safety function would have been achieved." |
| |
| The NRC resident inspector has been informed of this retraction by the |
| licensee. Notified R1DO (Cook). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35218 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 01/05/1999|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 15:18[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/05/1999|
+------------------------------------------------+EVENT TIME: 13:56[EST]|
| NRC NOTIFIED BY: JEFF MOSHER |LAST UPDATE DATE: 01/07/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LEN WERT R2 |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION REGARDING INOPERABILITY OF THE SPILLWAY EMERGENCY |
| DIESEL GENERATOR |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "At 1356 hours on 01/05/99, the Federal Emergency Regulatory Commission |
| (FERC) was notified of the inoperability of the North Anna spillway |
| emergency diesel generator in accordance with the requirements of |
| 18CFR12.10(a). The diesel generator failed its operability test due to the |
| engine water temperature being below the acceptable range of 165 - 195�F. |
| Water temperature during the test was 155�F. A work request has been |
| initiated to identify and correct the cause of this problem in a timely |
| manner. The diesel generator remains available." |
| |
| The licensee stated that the spillway emergency diesel generator is not |
| safety related and that the units are not in any limiting conditions for |
| operation as a result of this issue. |
| |
| In addition to the FERC, the licensee notified the NRC resident inspector. |
| |
| * * * UPDATE 1036 1/7/98 FROM M. WHALEN TAKEN BY STRANSKY * * * |
| |
| "At 0820 hours on 1/7/99, the Federal Energy Regulatory Commission (FERC) |
| was notified to retract a previous notification made at 1356 hours on |
| 1/5/99. The previous notification was made as a result of declaring the |
| North Anna spillway diesel generator inoperable due to engine water |
| temperature being below the acceptance range. Further evaluation and |
| consultation with the diesel vendor determined the spillway diesel generator |
| was in fact operable and able to perform its design function." |
| |
| The NRC resident inspector has been informed of this update by the licensee. |
| Notified R2DO (Wert). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35224 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 01/06/1999|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 15:26[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 01/06/1999|
+------------------------------------------------+EVENT TIME: 13:45[CST]|
| NRC NOTIFIED BY: DAVID WARD |LAST UPDATE DATE: 01/07/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |BRENT CLAYTON R3 |
|10 CFR SECTION: |JOHN STOLZ, NRR EO |
|AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOSEPH GIITTER, AEOD IRD |
|AESF 50.72(b)(2)(ii) ESF ACTUATION |GENE CANUPP FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| UNUSUAL EVENT DUE TO A LOSS OF OFFSITE POWER TO THE EMERGENCY BUSES WHILE IN |
| COLD SHUTDOWN |
| |
| At 1319 CST on 01/06/98, there was a loss of the 138-kV line supplying power |
| to the emergency reserve auxiliary transformer (ERAT) while the reserve |
| auxiliary transformer (RAT) was tagged/switched out of service due to |
| ongoing plant modifications. All three emergency diesel generators |
| automatically started and loaded properly, and they are currently supplying |
| power to the emergency buses. The non-vital buses are being energized via |
| the main power transformer back-feed lineup from the 345-kV source (normal |
| grid). Shutdown cooling is being maintained via the use of reactor water |
| cleanup, and vessel feed is from the control rod drive system. Residual |
| heat removal (RHR) train 'B' was in shutdown cooling prior to this event, |
| and the 'B' RHR pump tripped off when its emergency bus was initially |
| de-energized. The licensee stated that there were no reports of abnormal |
| functions other than the loss of the 138-kV line. |
| |
| A Notification of Unusual Event was declared at 1345 CST due to the loss of |
| the ERAT and RAT (when no sources of offsite power are available). The |
| licensee's procedures do not specifically address credit for having a |
| back-feed capability. The licensee plans to terminate the Unusual Event |
| when either the ERAT or RAT are returned to service and offsite power is |
| restored to safety systems. |
| |
| The cause of the loss of the 138-kV line is being investigated, but it is |
| currently believed to be from insulator damage to the 138-kV line near the |
| town of Clinton, Illinois. |
| |
| The unit has been in an extended shutdown since 09/06/96. |
| |
| The licensee notified the NRC resident inspector, the State of Illinois, and |
| DeWitt County Sheriff. |
| |
| ******************** UPDATE AT 1626 EST ON 01/06/99 FROM DAVID WARD TO |
| TROCINE ******************** |
| |
| The licensee reported that the automatic start of the emergency diesel |
| generators was an engineered safety feature actuation and that the cause of |
| the loss of the 138-kV line had not yet been determined. |
| |
| Shutdown cooling is still being maintained via the use of reactor water |
| cleanup, and vessel feed is from the control rod drive system. The licensee |
| stated that it would take 72 hours for boiling to occur if shutdown cooling |
| was not available. |
| |
| The NRC operations officer notified the R3DO (Clayton), NRR EO (Stolz), and |
| AEOD IRD (Giitter). |
| |
| ******************** UPDATE AT 1717 EST ON 01/06/99 FROM DAVID WARD TO |
| TROCINE ******************** |
| |
| The 'B' RHR pump was restored to service (in shutdown cooling) at 1600 CST. |
| Reactor water cleanup was running prior to the event, and remained in |
| service to provide an alternate means of shutdown cooling. |
| |
| The licensee plans to issue a press release and plans to notify the NRC |
| resident inspector. The NRC operations officer notified the R3DO (Clayton), |
| NRR EO (Zwolinski), and AEOD IRD (Giitter). |
| |
| ******************** UPDATE AT 1814 EST ON 01/06/99 FROM DAVID WARD TO |
| TROCINE ******************** |
| |
| The estimated time for restoration of RAT power is approximately 1800 CST, |
| and the estimated time for exiting the Unusual Event is approximately 2100 |
| CST. |
| |
| The NRC operations officer notified the R3DO (Clayton), NRR EO (Zwolinski), |
| and AEOD IRD (Giitter). |
| |
| ******************** UPDATE AT 1916 EST ON 01/06/99 FROM DAVID WARD TO |
| TROCINE ******************** |
| |
| Offsite power was restored to the RAT at approximately 1750 CST, but it is |
| not yet supplying vital loads. Vital loads are still being supplied via the |
| emergency diesel generators. The estimated time for exiting the Unusual |
| Event is still approximately 2100 CST. Spent fuel pool cooling was |
| maintained throughout this event. |
| |
| The NRC operations officer notified the R3DO (Clayton), NRR EO (Zwolinski), |
| and AEOD IRD (Giitter). |
| |
| ******************** UPDATE AT 2016 EST ON 01/06/99 FROM MAXWELL KIER TO |
| TROCINE ******************** |
| |
| Vital loads are still being supplied via the emergency diesel generators. |
| The licensee currently expects the RAT to supply vital loads at |
| approximately 2100 CST. The estimated time for exiting the Unusual Event is |
| still approximately 2100 CST. |
| |
| The NRC operations officer notified the R3DO (Clayton), NRR EO (Zwolinski), |
| and AEOD IRD (Giitter). |
| |
| ******************** UPDATE AT 2116 EST ON 01/06/99 FROM MAXWELL KIER TO |
| TROCINE ******************** |
| |
| The cause of the loss of the 138-kV line was determined to be a pole over |
| north of Clinton that shorted a couple of phases. Repairs are in progress, |
| and the estimated time of completion is unknown. The estimated time for |
| exiting the Unusual Event is now approximately 2130 CST. |
| |
| The NRC operations officer notified the R3DO (Clayton), NRR EO (Zwolinski), |
| and AEOD IRD (Giitter). |
| |
| ******************** UPDATE AT 2216 EST ON 01/06/99 FROM MAXWELL KIER TO |
| TROCINE ******************** |
| |
| The licensee is currently swapping emergency buses from the emergency diesel |
| generators to the RAT. The licensee is also in the process of restoring the |
| ERAT to service. Repairs to the 138-kV line are complete. The estimated |
| time for exiting the Unusual Event is still approximately 2130 CST. |
| |
| The NRC operations officer notified the R3DO (Clayton), NRR EO (Zwolinski), |
| and AEOD IRD (Giitter). |
| |
| ******************** UPDATE AT 2314 EST ON 01/06/99 FROM MAXWELL KIER TO |
| TROCINE ******************** |
| |
| The root cause of the 138-kV line going down was determined to be down guys |
| on a corner pole where the line taps to Clinton. The guys were possibly |
| severed by a snow plow. This allowed the pole to lean causing the static |
| shield to contact one of the phases. |
| |
| The division 1 and 2 emergency buses are currently being supplied from the |
| RAT, and the licensee is currently placing the division 3 emergency bus on |
| the RAT. The new estimated time for exiting the Unusual Event is |
| approximately 2245 CST. |
| |
| The NRC operations officer notified the R3DO (Clayton), NRR EO (Zwolinski), |
| and AEOD IRD (Giitter). |
| |
| * * * UPDATE 0010 1/7/99 FROM M. KIER TAKEN BY STRANSKY * * * |
| |
| The UE was terminated at 2306 CST on 1/6/99. One offsite power source has |
| been restored to the emergency busses, and the other offsite source is |
| currently being restored. The NRC resident inspector has been informed of |
| the termination. Notified R3DO (Clayton), EO (Zwolinski). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35225 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 01/07/1999|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 12:16[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 01/07/1999|
+------------------------------------------------+EVENT TIME: 10:30[EST]|
| NRC NOTIFIED BY: HARLAN HANSON |LAST UPDATE DATE: 01/07/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |WILLIAM COOK R1 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| EMERGENCY RESPONSE DATA SYSTEM (ERDS) INOPERABLE |
| |
| The licensee reported that their ERDS system was discovered to be inoperable |
| during quarterly system testing because of a bad phone line or modem at |
| 1030am on 1/7/99. Efforts to restore the phone line/modem were not |
| successful within the one hour allotted per the PSE&G Event Classification |
| Guidance. These efforts will continue. |
| |
| The licensee will inform the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35226 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: STATE OF CALIFORNIA |NOTIFICATION DATE: 01/07/1999|
|LICENSEE: CEDARS-SINAI HOSPITAL |NOTIFICATION TIME: 16:23[EST]|
| CITY: Los Angeles REGION: 4 |EVENT DATE: 01/06/1999|
| COUNTY: Los Angeles STATE: CA |EVENT TIME: 12:00[PST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 01/07/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOSEPH TAPIA R4 |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DONALD BUNN | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION |
| |
| The licensee was using an investigative new drug (IND) Rhenium-188 when the |
| isotope leaked out of its container and into the blood stream of the |
| patient. Re-188 is used to prevent restenosis (the collapsing of the blood |
| vessel) during angioplasty. The licensee was authorized to use up to 200 |
| mCi of material during this procedure, but the exact quantity used was not |
| known at the time of this report. The licensee is in the process of |
| developing a dose estimate, however negative health effects are not |
| expected. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 35227 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: USAF RADIOISOTOPE COMMITTEE |NOTIFICATION DATE: 01/07/1999|
|LICENSEE: USAF RADIOISOTOPE COMMITTEE |NOTIFICATION TIME: 16:29[EST]|
| CITY: GLENDALE REGION: 4 |EVENT DATE: 01/07/1999|
| COUNTY: STATE: AZ |EVENT TIME: 15:30[EST]|
|LICENSE#: 42-23539-01AF AGREEMENT: Y |LAST UPDATE DATE: 01/07/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JOSEPH TAPIA R4 |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MAJOR JIM HICKS | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| F-16 CRASHED CONTAINING 8�Ci OF AMERICIUM-241 |
| |
| An Air Force F-16 crashed near Luke Air Force base, Arizona. The plane |
| contained an 8 �Ci Am-241 source. The pilot and navigator ejected safely. |
| |
| |
| The Air Force is responding to the crash site and will perform a search for |
| the source. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35228 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 01/07/1999|
| UNIT: [1] [2] [] STATE: GA |NOTIFICATION TIME: 16:44[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/07/1999|
+------------------------------------------------+EVENT TIME: 16:28[EST]|
| NRC NOTIFIED BY: TOM TYNAN |LAST UPDATE DATE: 01/08/1999|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LEN WERT R2 |
|10 CFR SECTION: | |
|AENS 50.72(b)(1)(v) ENS INOPERABLE | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| FTS AND COMMERCIAL PHONE LINES OUT OF SERVICE |
| |
| The licensee notified the NRC via cellular phone that both their FTS-2000 |
| and their commercial lines were unavailable for dial out. However, the |
| commercial lines could be accessed by dialing in from the Operations Center. |
| The licensee is troubleshooting this problem and believes it may be related |
| to some other work (digging) in progress. |
| |
| The licensee informed the NRC resident inspector. |
| |
| * * * UPDATE 0153 1/8/99 FROM SHFLIGER TAKEN BY STRANSKY * * * |
| |
| All telephones are now working properly. The NRC resident inspector will be |
| informed by the licensee. Notified R2DO (Wert). |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021