Event Notification Report for January 20, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/19/2000 - 01/20/2000

                              ** EVENT NUMBERS **

36596  36601  36604  36605  36606  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36596       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEABROOK                 REGION:  1  |NOTIFICATION DATE: 01/17/2000|
|    UNIT:  [1] [] []                 STATE:  NH |NOTIFICATION TIME: 06:32[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        01/17/2000|
+------------------------------------------------+EVENT TIME:        05:38[EST]|
| NRC NOTIFIED BY:  MIKE DAVID                   |LAST UPDATE DATE:  01/19/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |GLENN MEYER          R1      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| SECURITY REPORT. FITNESS-FOR-DUTY QUESTIONED DUE TO INATTENTIVENESS.         |
| IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. CONTACT THE NRC        |
| OPERATIONS CENTER FOR ADDITIONAL DETAILS.                                    |
|                                                                              |
| * * *  UPDATE 1140EST ON 1/19/00 FROM MATTHEW ARSENAULT TO S.SANDIN * * *    |
|                                                                              |
| THIS REPORT IS BEING RETRACTED BASED ON THE FOLLOWING:                       |
|                                                                              |
| "On January 17, 2000, at 6:32 EST, North Atlantic Energy Service Corporation |
| (North Atlantic) submitted a 1-hour report to the Nuclear Regulatory         |
| Commission pursuant to 10 CFR 73.71 regarding a Security Officer that was    |
| discovered to be inattentive to duty (NRC Event Report 36596).               |
|                                                                              |
| "Subsequent to the report and after a thorough review, it was determined     |
| that this incident was loggable and did not meet the criteria for a 1-hour   |
| report.  Specifically, this condition did not constitute an uncompensated    |
| loss as defined in Regulatory Guide 5.62 because the original capability was |
| restored within 10 minutes of discovery of the event.  Additionally,         |
| consistent with the guidance provided in Generic Letter 91-03, events        |
| involving inattentive security personnel can be logged if they are properly  |
| compensated for in accordance with Regulatory Guide 5.62 and NUREG-1304.     |
| Therefore, North Atlantic retracts the 1-hour report.  This event has been   |
| captured in the event log."                                                  |
|                                                                              |
| The licensee will inform the NRC resident inspector.  Notified R1DO          |
| (Hinson).                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36601       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 01/18/2000|
|    UNIT:  [1] [2] [3]               STATE:  AZ |NOTIFICATION TIME: 11:41[EST]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        01/18/2000|
+------------------------------------------------+EVENT TIME:        09:25[MST]|
| NRC NOTIFIED BY:  DAN MARKS                    |LAST UPDATE DATE:  01/19/2000|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LINDA SMITH          R4      |
|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  |
|3     N          Y       100      Power Operation  |100      Power Operation  |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF COMMERCIAL TELEPHONE SERVICE                                         |
|                                                                              |
| The licensee reported that all U.S. West commercial telephone service to the |
| site (including the ENS)  has been lost due to a problem offsite.  The       |
| licensee is attempting to contact U.S. West to determine the cause of the    |
| problem and estimate time to restore.                                        |
|                                                                              |
| The NRC resident inspector will be informed of this event by the licensee.   |
|                                                                              |
| ******************** UPDATE AT 1916 ON 01/18/00 FROM  DAN MARKS TO LEIGH     |
| TROCINE ********************                                                 |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "The following event description is based on information currently           |
| available.  If through subsequent reviews of this event, additional          |
| information is identified that is pertinent to this event or alters the      |
| information being provided at this time, a followup notification will be     |
| made via the ENS or under the reporting requirements of 10 CFR 50.73."       |
|                                                                              |
| "NOTE: THIS ENS WORKSHEET IS A FOLLOW-UP TO ENS ID 36601, PERFORMED AT 09:41 |
| MST.  SINCE U.S. WEST LINES WERE AFFECTED, THE INITIAL CALL WAS MADE VIA A   |
| CELLULAR TELEPHONE."                                                         |
|                                                                              |
| "On January 18, 2000, at approximately 0925 MST, Palo Verde Units 1, 2, and  |
| 3 determined that the ENS telephones were inoperable.  This was related to   |
| the offsite damage to a 200-pair telecommunications cable affecting Palo     |
| Verde.  The initial call was placed from the Nuclear Regulatory Affairs      |
| Director's cellular telephone, and that phone number was also provided to    |
| the [headquarters operations officer] if followup was necessary prior to     |
| restoration of the ENS."                                                     |
|                                                                              |
| "The current prognosis for full restoration of the ENS is approximately 2400 |
| MST.  If the Palo Verde Units 1, 2, or 3 cannot be reached via the ENS,      |
| [commercial] ... phone numbers are available.  [Call the NRC operations      |
| officer for site contact numbers.] ..."                                      |
|                                                                              |
| "Emergency Plan notification system backups for communication with State and |
| County agencies were confirmed to remain operable; therefore, this           |
| notification was only for the loss of ENS and did not reflect a loss of      |
| emergency assessment or notification capability."                            |
|                                                                              |
| "There is no corresponding 10 CFR 50.73 reporting requirement.  Palo Verde   |
| does not expect to followup this report with a Licensee Event Report         |
| (LER)."                                                                      |
|                                                                              |
| "Palo Verde [plans to] complete a followup notification when full capability |
| is restored."                                                                |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations        |
| officer notified the R4DO (Smith).                                           |
|                                                                              |
| * * * UPDATE 0006EST ON 1/19/2000 FROM BRAD ROBINSON TO S.SANDIN * * *       |
|                                                                              |
| The ENS phones have been restored to complete functionality at 2206MST.  The |
| licensee notified the NRC resident inspector.  Notified R4DO(Smith).         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36604       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 01/19/2000|
|    UNIT:  [1] [2] []                STATE:  TX |NOTIFICATION TIME: 15:46[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        01/19/2000|
+------------------------------------------------+EVENT TIME:        14:24[CST]|
| NRC NOTIFIED BY:  DON CERNY                    |LAST UPDATE DATE:  01/19/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LINDA SMITH          R4      |
|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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY THAT UNIT SPECIFIC LOADS WERE ON COMMON BUSES                      |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "FSAR section 1A(B) for compliance to Reg Guide 1.81 states that [the        |
| Comanche Peak] design complies with the provisions of Revision 1 of this Reg |
| Guide.  Contrary to the above, unit specific [118-volt AC] loads fed from    |
| common buses XEC1-1 and XEC2-1 were shared between two units."               |
|                                                                              |
| The licensee stated that affected loads involve a lot of different equipment |
| and systems but did not specify which equipment or systems.  The licensee    |
| also stated that the units are not currently in any technical specification  |
| limiting conditions for operation as a result of this issue because the      |
| loads are now aligned to an alternate power supply.  Corrective actions have |
| not yet been determined.                                                     |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36605       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 01/19/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 17:59[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        01/19/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        09:00[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  01/19/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |DAVID HILLS          R3      |
|  DOCKET:  0707002                              |WAYNE HODGES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DALE NOEL                    |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|OCBB 76.120(c)(2)(ii)    EQUIP DISABLED/FAILS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FAILURE OF HIGH PRESSURE FIRE WATER SPRINKLER SYSTEMS TO MEET SYSTEM         |
| OPERABILITY REQUIREMENTS (24-Hour Report) - (Refer the event #36018 for a    |
| similar event at Portsmouth and refer to event #35790 and event #36552 for   |
| related events at Paducah.)                                                  |
|                                                                              |
| The following text is a portion of a facsimile received from Portsmouth:     |
|                                                                              |
| "On 01/19/00 at approximately 0900 hours during the scheduled semi-annual    |
| walkdown of the X-330 Process Building high pressure fire water (HPFW)       |
| systems, the Plant Shift Superintendent (PSS) was notified that sprinkler    |
| systems #284 and #365 were not capable of meeting system operability         |
| requirements due to corrosion problems identified on adjacent sprinkler      |
| heads."                                                                      |
|                                                                              |
| "Two adjacent heads on system #284 and three adjacent heads on system #365   |
| were identified with corrosion around the valve seat.  This condition        |
| prevents the heads from being able to actuate at normal water pressure.      |
| When two adjacent heads are inoperable, the system is considered unable to   |
| perform its design function.  The PSS declared the affected sprinkler        |
| systems inoperable, and [technical safety requirement (TSR)] required        |
| actions were initiated and completed."                                       |
|                                                                              |
| "Further inspections of the Process Building sprinkler systems are planned.  |
| This report will be updated if additional sprinkler systems are determined   |
| to be inoperable."                                                           |
|                                                                              |
| "There was no loss of hazardous/radioactive material or                      |
| radioactive/radiological contamination exposure as a result of this event."  |
|                                                                              |
| At the time of this event notification, Portsmouth personnel had completed   |
| repairs and were in the process of closing out the paperwork to be able to   |
| declare the systems operable again.                                          |
|                                                                              |
| Portsmouth personnel notified the NRC resident inspector and a Department of |
| Energy site representative.                                                  |
|                                                                              |
| (Call the NRC operations officer for a site contact telephone number.)       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36606       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 01/19/2000|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 21:59[EST]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        01/19/2000|
+------------------------------------------------+EVENT TIME:        14:55[CST]|
| NRC NOTIFIED BY:  CAROL KRONICK                |LAST UPDATE DATE:  01/19/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID HILLS          R3      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD  |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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       85       Power Operation  |85       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF A LOOSE STEM NUT AND THE INABILITY TO MANUALLY OPERATE A SAFE   |
| SHUTDOWN MAKEUP PUMP (SSMP) INJECTION VALVE FOLLOWED BY DISCOVERY THAT THE   |
| VALVE WAS NOT FULLY CLOSED                                                   |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "On January 19, 2000, at 1357 [CST], the MO 2-2901-8 [valve] (SSMP injection |
| to Unit 2) was taken [out of service] for planned maintenance on the valve   |
| position limit switches.  At 1455 [CST], the Maintenance Supervisor notified |
| the control room that the stem nut was found loose and [that] the valve      |
| could not be manually operated.  For Unit 2, a 14-day technical              |
| specification [(TS) limiting condition for operation (LCO)] was entered per  |
| TS 3.8.J, and a 14-day LCO for administrative technical requirements (ATR)   |
| was entered.  At 1605 [CST,] it was determined that the valve was not fully  |
| closed, and the SSMP system [was] declared inoperable to Unit 1.  [As a      |
| result, a] 14-day LCO for [TSs] and a 14-day ATR [were] entered for Unit 1.  |
| A plan is being developed to repair/correct the MO 2-2901-8 [valve]."        |
|                                                                              |
| "It was determined at 2040 [CST] that this event is reportable ... ."        |
|                                                                              |
| The licensee stated that both the pump and the valve have quarterly          |
| surveillances and that the surveillances were up to date.                    |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.                     |
+------------------------------------------------------------------------------+


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