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Event Notification Report for October 7, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/06/1999 - 10/07/1999

                              ** EVENT NUMBERS **

36263  36264  36265  36266  36267  36268  36269  36270  

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36263       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  SWAGELOK COMPANY                     |NOTIFICATION DATE: 10/06/1999|
|LICENSEE:  SWAGELOK COMPANY                     |NOTIFICATION TIME: 09:48[EDT]|
|    CITY:  Solon                    REGION:  3  |EVENT DATE:        10/04/1999|
|  COUNTY:                            STATE:  OH |EVENT TIME:             [EDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  10/06/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN KINNEMAN        R1      |
|                                                |BRIAN BONSER         R2      |
+------------------------------------------------+JOHN JACOBSON        R3      |
| NRC NOTIFIED BY:  BRUCE FLUSCHE (Fax)          |KRISS KENNEDY        R4      |
|  HQ OPS OFFICER:  LEIGH TROCINE                |VERN HODGE           NRR     |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POSSIBLE 10-CFR-PART-21 REPORT REGARDING A POSSIBLE DEFECT IN A SWAGELOK     |
| TUBE FITTING                                                                 |
|                                                                              |
| The following text is a portion of a facsimile submitted by Swagelok         |
| Company:                                                                     |
|                                                                              |
| "This is a preliminary notification of a possible defect in a Swagelok tube  |
| fitting, part number SS-400-3-4TTM, male branch tee.  A drawing of the part  |
| is included with this notification.  We are also notifying each of the       |
| involved utilities."                                                         |
|                                                                              |
| "We became aware of this on October 4, 1999."                                |
|                                                                              |
| "The defect is a crack in the seat of the fitting.  We are continuing our    |
| analysis of the part and will provide further details in accordance with NRC |
| timetables."                                                                 |
|                                                                              |
| "[The] following are the six utilities to whom we have sold these parts:     |
|                                                                              |
| Georgia Power [Company], Plant Vogtle, ... , 10 pcs. ... [;]                 |
| Duke Power Company, Oconee Nuclear Station, ... ,100 pcs. ... [;]            |
| Arizona Public Service Co., Palo Verde Nuclear Generating Station, ... , 15  |
| pcs. ... [;]                                                                 |
| North Atlantic Energy Service Co., ... , Seabrook Station, ... ,10 pcs. ...  |
| [;]                                                                          |
| Virginia Power, Surry Power Station, ... , 3 pcs. ... [; and]                |
| Omaha Public Power District, Ft. Calhoun Nuclear Station, ... , 10 Pcs. ...  |
| ."                                                                           |
|                                                                              |
| (Call the NRC operations officer for Swagelok contact information.)          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36264       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WATERFORD                REGION:  4  |NOTIFICATION DATE: 10/06/1999|
|    UNIT:  [3] [] []                 STATE:  LA |NOTIFICATION TIME: 12:49[EDT]|
|   RXTYPE: [3] CE                               |EVENT DATE:        10/06/1999|
+------------------------------------------------+EVENT TIME:        10:55[CDT]|
| NRC NOTIFIED BY:  OSCAR PIPKINS                |LAST UPDATE DATE:  10/06/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KRISS KENNEDY        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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| FIRE PROTECTION SYSTEM SPRINKLER FOR 'B' EMERGENCY DIESEL GENERATOR          |
| INOPERABLE                                                                   |
|                                                                              |
| The licensee determined that the fire protection sprinkler system FPM-4B     |
| could not meet the pressure requirements for the Fire Protection Code        |
| NFA-13.  The system was declared inoperable, but in service and a continuous |
| fire watch was posted as an immediate compensatory measure.  The system is   |
| for fire protection in the 'B' emergency diesel generator (EDG) room, the    |
| EDG remains operable due to the fire watch.  The condition was discovered    |
| during a review of sprinkler system hydraulic calculations in response to an |
| earlier condition report.                                                    |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36265       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CRYSTAL RIVER            REGION:  2  |NOTIFICATION DATE: 10/06/1999|
|    UNIT:  [3] [] []                 STATE:  FL |NOTIFICATION TIME: 14:57[EDT]|
|   RXTYPE: [3] B&W-L-LP                         |EVENT DATE:        08/06/1999|
+------------------------------------------------+EVENT TIME:             [EDT]|
| NRC NOTIFIED BY:  W. BAUDHAUER                 |LAST UPDATE DATE:  10/06/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRIAN BONSER         R2      |
|10 CFR SECTION:                                 |VERN HODGE (FAX)             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          N       0        Hot Shutdown     |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT - DAMAGED SAFETY GRADE ELECTRICAL CABLING FOUND IN     |
| SUPPLY                                                                       |
|                                                                              |
| "On August 31, 1999, damage to a new power cable being installed in a        |
| non-safety-related application under Modification Approval Record MAR        |
| 98-04-06-01 (Instrument Air Compressor Upgrade) was identified. The          |
| insulation on one conductor of three conductor cable (BICC Brand Rex Company |
| power cable #1108582, 1 Kv, 3/C, #2/0, Class B, 90C, XLPE Insulated, Black   |
| Jacket) was found to be damaged when the outer jacket was                    |
| removed for termination. This was the first issuance of the cable (4 Reels   |
| containing approximately 4,000 feet total in stock), which had been procured |
| as safety grade and Environmentally Qualified (EQ) (PO #F830409D). A total   |
| of six samples of the pulled cable were inspected. Damage to the same        |
| conductor was found in all six samples. The cable appeared to have been      |
| damaged during fabrication rather than by cable pulling techniques.          |
|                                                                              |
| "The vendor stated that the damage was created during the cabling process    |
| while combining the three conductors just prior to closing. The damaged      |
| conductor fell off the cabling unit pulley due to loss of tension, causing   |
| the insulation to be scraped                                                 |
|                                                                              |
| "Although never used in the plant, the subject cable could have been used in |
| a safety-related application in a harsh environment such as the Reactor      |
| Building or Intermediate Building. In a harsh environment created under      |
| accident conditions, the damaged cable insulation could allow the cable      |
| conductor to "leak" through moisture to nearby grounds, thus tripping and    |
| rendering inoperable, equipment downstream of the fault. Normally, conductor |
| insulation is the primary barrier to leaks in loss of Coolant Accident       |
| (LOCA) tests when jacket material occasionally cracks. Also, if the cable    |
| was installed in a metal cabinet so that the cable outer jacket had been     |
| stripped near the defect to allow cable termination, the damaged cable       |
| insulation on the one conductor could potentially allow contact with the     |
| cabinet or a nearby ground during a seismic event and cause the circuit to   |
| malfunction. In either case, safety-related loads required to mitigate the   |
| consequences of an accident or to perform a safety-related function, could   |
| be impacted to the extent that a substantial safety hazard could be          |
| created.                                                                     |
|                                                                              |
| "The above evaluation was completed on October 4, 1999. The FPC              |
| director/responsible officer was notified of the above determination on      |
| October 6, 1999. The vendor has been notified of FPC's intent to report this |
| issue under 10CFR21.21."                                                     |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36266       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY            REGION:  1  |NOTIFICATION DATE: 10/06/1999|
|    UNIT:  [1] [2] []                STATE:  PA |NOTIFICATION TIME: 18:15[EDT]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        10/06/1999|
+------------------------------------------------+EVENT TIME:        17:45[EDT]|
| NRC NOTIFIED BY:  DAUGHERTY                    |LAST UPDATE DATE:  10/06/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        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  |
|2     N          Y       90       Power Operation  |90       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| ERROR FOUND IN LARGE BREAK LOCA ANALYSIS                                     |
|                                                                              |
| "Westinghouse Letter DLC-99-768 reported errors found in the Large Break     |
| LOCA analysis for both Beaver Valley units.  These errors resulted in        |
| calculated maximum Peak Clad Temperatures >2200F with out taking credit for |
| any other available margins.  Per 10CFR50.46.a.3.(ii), any change or error   |
| correction that results in a calculated ECCS performance (where Peak Clad    |
| Temperature is not maintained <2200F) Is reportable per 10CFR50.72          |
|                                                                              |
| "It should be noted that Westinghouse Letter DLC-99-768 proposed a more      |
| conservative restriction on FQ limits for both units, and a more             |
| conservative limit on Steam Generator tube plugging at unit 2 that would     |
| overcome the effects of the reported errors.  These limits are presently     |
| being met and have been met for the time periods of the present cycles at    |
| both units, so that the proposed analysis appears to be valid.  Engineering  |
| evaluation is pending for final approval of these proposals."                |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36267       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 10/06/1999|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 18:28[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/06/1999|
+------------------------------------------------+EVENT TIME:        16:40[EDT]|
| NRC NOTIFIED BY:  DENNIS MAY                   |LAST UPDATE DATE:  10/06/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|NLCO                     TECH SPEC LCO A/S      |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       99       Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| BOTH TRAINS OF LOW PRESSURE COOLANT INJECTION DECLARED INOPERABLE            |
|                                                                              |
| During periodic inspections, technicians discovered multiple loose battery   |
| terminal connections on both UPS-1A and UPS-1B batteries.  The licensee was  |
| uncertain of the operability of the batteries and conservatively declared    |
| both trains of low pressure coolant injection (LPCI) inoperable.  This put   |
| them in a 24-hour Technical Specification action statement (3.5.A.6) to      |
| bring the plant to hot shutdown.  Electrical maintenance is on site          |
| tightening connections and inspecting all battery connections.  The licensee |
| does not anticipate having to shutdown as electrical maintenance is working  |
| now.  An investigation into the event will follow up the event.              |
|                                                                              |
| The licensee notified the NRC Resident Inspector and the State of Vermont    |
| Nuclear Engineer.                                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36268       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 10/06/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 18:30[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/06/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        17:03[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  10/07/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JOHN JACOBSON        R3      |
|  DOCKET:  0707002                              |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEITH WILLIAMSON             |                             |
|  HQ OPS OFFICER:  FANGIE JONES                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INFORMATION REPORT ON RUPTURE OF CIRCULATING WATER HEADER FOLLOWED BY AN     |
| OFFSITE NOTIFICATION (4-HOUR NOTIFICATION)                                   |
|                                                                              |
| The plant suffered a rupture in a 6-inch header on the plant circulating     |
| water header that does not affect present plant operation.  Work is in       |
| progress to isolate the leak.  Several thousand gallons of water have been   |
| released on site, and environmental sampling of the site outfalls is         |
| underway to determine if any release offsite of chlorine (water additive)    |
| has taken place.                                                             |
|                                                                              |
| Portsmouth personnel have notified the NRC resident inspector.               |
|                                                                              |
| (Call the NRC operations officer for a contact telephone number.)            |
|                                                                              |
| ******************** UPDATE AT 0103 ON 10/07/99 FROM ERIC SPAETH TO LEIGH    |
| TROCINE ********************                                                 |
|                                                                              |
| The following text is a portion of a facsimile received from Portsmouth:     |
|                                                                              |
| "At approximately 1703 hrs on 10/06/99, a recirculating cooling water line   |
| rupture occurred on the plant.  A 6-inch line rupture caused a significant   |
| increase in flow through an NPDES outfall.  Monitoring has not determined a  |
| permitted limit exceedance or impact to local water tributaries.  However,   |
| [at 0008 hrs on 10/07/99,] a courtesy notification to [the Ohio              |
| Environmental Protection Agency (OEPA)] was made to advise of this upset     |
| condition."                                                                  |
|                                                                              |
| "[This is a 4-hour] notification to the NRC due to [the] plant notifying     |
| [another] government agency [ ... ]."                                        |
|                                                                              |
| "There was no loss of hazardous/radioactive material or                      |
| radioactive/radiological contamination exposure as a result of this event."  |
|                                                                              |
| Portsmouth personnel plan to notify the NRC resident inspector and the       |
| Department of Energy site representative.  The NRC operations center         |
| notified the R3DO (Jacobson), NMSS EO (Greeves), and IRO (Miller).           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36269       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  STATE OF ILLINOIS                    |NOTIFICATION DATE: 10/07/1999|
|LICENSEE:  RUSH-PRES-ST. LUKE'S MEDICAL CENTER  |NOTIFICATION TIME: 00:43[EDT]|
|    CITY:                           REGION:  3  |EVENT DATE:        10/05/1999|
|  COUNTY:                            STATE:  IL |EVENT TIME:             [CDT]|
|LICENSE#:  IL-01766-01           AGREEMENT:  Y  |LAST UPDATE DATE:  10/07/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN JACOBSON        R3      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  PATRICIA LARKINS (NRC)       |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT OF A NOVOSTE CORPORATION BETA-CATHETER TREATMENT      |
| DEVICE DRIVE MECHANISM FAILURE AT ST. LUKE'S MEDICAL CENTER  (The facility's |
| location was not provided.)                                                  |
|                                                                              |
| The following text is a portion of an E-mail sent to the NRC operations      |
| center from the NRC Office of State Programs (Patricia Larkins) at 1650 on   |
| 10/06/99 which enclosed another E-mail from the State of Illinois (Bruce     |
| Sanza) to the NRC (Patricia Larkins) at 1409 on 10/05/99:                    |
|                                                                              |
| "FYI.  The license number is IL-01766-01"                                    |
|                                                                              |
| "-----Original Message-----  From: Gulczynski, Andy                          |
| Sent: Tuesday, October 05, 1999 12:05 PM                                     |
| To: Sanza, Bruce; Klinger, Joe; Eastvold, Paul                               |
| Cc: (ORS, Glen Ellyn DRM Staff)                                              |
| Subject: Reported Drive Mechanism Failure in Novoste Corporation             |
| Beta-Catheter Treatment Device "                                             |
|                                                                              |
| "Glenn Sullivan, RSO at Rush-Pres-St. Luke's Medical Center, [ ... ], just   |
| called me to report an event which occurred this morning."                   |
|                                                                              |
| "A patient was being treated with a Novoste Corporation Beta-Cath System     |
| (Model SRO.S03 using Novoste Source Train 139/99 in transfer device 7Z519).  |
| The device is used to treat arterial occlusions.   This system contains 56   |
| mCi of Sr-90 as of April 8, 1999, contained in 16 active seeds.  The source  |
| 'train' contains a total of 18 seeds, two of which are 'dummies', located at |
| the beginning and the end of the source train.  The sources are driven in to |
| and out of the catheter using saline solution (water pressure).  This system |
| is an 'all or nothing' system, meaning all the seeds are used in each        |
| treatment."                                                                  |
|                                                                              |
| "At the conclusion of today's treatment, the staff could not visually verify |
| the presence of all the sources within the machine.  They immediately        |
| removed the catheter from the patient; surveyed the patient, the catheter,   |
| and the room; and found no sources present.  They then connected the         |
| catheter to the machine and activated the drive mechanism.  Six active       |
| sources and one dummy source came out, which they placed into a shielded     |
| container.  They activated the drive mechanism again and 9 active sources,   |
| and one dummy source came out.  (This left one source unaccounted for.)      |
| They then surveyed the machine and confirmed the presence of the last source |
| within the machine, though they do not know exactly where it is located."    |
|                                                                              |
| "The patient suffered no adverse effects and received no unplanned exposure  |
| as a result of this event."                                                  |
|                                                                              |
| "Glenn Sullivan is preparing a written report, which will be sent to our     |
| Department."                                                                 |
|                                                                              |
| (Call the NRC operations officer for a licensee contact name and telephone   |
| number.)                                                                     |
|                                                                              |
| ******************** UPDATE AT 0044 ON 10/07/88 BY LEIGH TROCINE             |
| ********************                                                         |
|                                                                              |
| The following text is a portion of an E-mail sent to the NRC operations      |
| center from the NRC Office of State Programs (Patricia Larkins) at 1651 on   |
| 10/06/99 which enclosed another E-mail from the State of Illinois (Bruce     |
| Sanza) to the NRC (Patricia Larkins) at 1432 on 10/05/99:                    |
|                                                                              |
| "-----Original Message-----  From: Gulczynski, Andy                          |
| Sent: Tuesday, October 05, 1999 1:31 PM                                      |
| To: Sanza, Bruce; Klinger, Joe; Eastvold, Paul                               |
| Cc: (ORS, Glen Ellyn DRM Staff)                                              |
| Subject: Update to Novoste Corporation Beta Cath Event"                      |
|                                                                              |
| "Glenn Sullivan called again to inform us that a Novoste Corporation         |
| Representative will be at Rush-Pres-St. Luke's Medical Center tomorrow to    |
| investigate the cause of this event.  Glenn will keep us informed of any     |
| new                                                                          |
| developments. "                                                              |
|                                                                              |
| The NRC operations officer notified the R3DO (Jacobson) and NMSS EO          |
| (Greeves).                                                                   |
|                                                                              |
| ******************** UPDATE AT 0045 ON 10/07/88 BY LEIGH TROCINE             |
| ********************                                                         |
|                                                                              |
| The following text is a portion of an E-mail sent to the NRC operations      |
| center from the NRC Office of State Programs (Patricia Larkins) at 1653 on   |
| 10/06/99 which enclosed another E-mail from the State of Illinois (Bruce     |
| Sanza) to the NRC (Patricia Larkins) at 1436 on 10/06/99:                    |
|                                                                              |
| "-----Original Message-----  From: Gulczynski, Andy                          |
| Sent: Wednesday, October 06, 1999 1:35 PM                                    |
| To: Sanza, Bruce; Klinger, Joe; Eastvold, Paul                               |
| Cc: (ORS, Glen Ellyn DRM Staff); Merrihew, George                            |
| Subject: Update on Novoste Beta-Cath System"                                 |
|                                                                              |
| "Glenn Sullivan called me with an update to the Novoste Beta-Cath source     |
| drive mechanism failure:"                                                    |
|                                                                              |
| "Novoste service personnel were there today and dismantled the machine.      |
| They found the missing source in the 'belly' of the machine stuck to a       |
| magnet.  They don't know how or why yet.  They left the sources with Glenn   |
| and took the machine to their facility to perform tests on it, presumably to |
| figure out the root cause(s) of the failure."                                |
|                                                                              |
| "One of the sources involved in the event appeared to be damaged.  All of    |
| the sources were leak tested and none, including the damaged one, were       |
| leaking.  Glenn said that he would package the sources and ship them to the  |
| supplier."                                                                   |
|                                                                              |
| "A written report from Glenn Sullivan will be sent to our Department."       |
|                                                                              |
| The NRC operations officer notified the R3DO (Jacobson) and NMSS EO          |
| (Greeves).                                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36270       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 10/07/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 01:03[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        10/06/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        21:10[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  10/07/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JOHN JACOBSON        R3      |
|  DOCKET:  0707002                              |JOHN GREEVES         NMSS    |
+------------------------------------------------+CHARLES MILLER       IRO     |
| NRC NOTIFIED BY:  ERIC SPAETH                  |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
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                                   EVENT TEXT                                   
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| NRC BULLETIN 91-01 RESPONSE (4-HOUR REPORT)                                  |
|                                                                              |
| The following text is a portion of a facsimile received from Portsmouth:     |
|                                                                              |
| "On 10/06/99 at 2110 hrs, the Plant Shift Superintendent (PSS) was notified  |
| by NCS Engineering, that an Nuclear Criticality Safety Approval (NCSA)       |
| requirement was not being maintained in the X-333 process building during a  |
| maintenance evolution.  Maintenance personnel, while working on seal exhaust |
| pumps, removed the filter from the demister without prior non-destructive    |
| analysis (NDA) being completed."                                             |
|                                                                              |
| "Requirement #12 of NCSA-033_016.AO1 states in part [that] seal exhaust      |
| pumps/demisters shall be drained of oil then NDA measured for U-235 content  |
| prior to removal."                                                           |
|                                                                              |
| "At the direction of the [PSS,] the requirements for an NCS anomalous        |
| condition were initiated, and the area was boundaried off."                  |
|                                                                              |
| "There was no loss of hazardous/radioactive material or                      |
| radioactive/radiological contamination exposure as a result of this event."  |
|                                                                              |
| "SAFETY SIGNIFICANCE OF EVENTS:  An NDA measurement was not obtained;        |
| however, the demister was drained of oil.  Therefore, an unsafe mass is not  |
| anticipated.  The maximum enrichment for the seal exhaust is 3% U-235.       |
| Spacing was maintained; therefore, the overall safety [significance] is low. |
| (At the enrichment involved, the component is a favorable geometry)."        |
|                                                                              |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW           |
| CRITICALITY COULD OCCUR):  In order for criticality to occur, a spacing      |
| violation would have to occur as well as a failure to NDA the equipment      |
| prior to removal."                                                           |
|                                                                              |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.):    |
| Spacing [was] maintained.  Mass [was] assumed [to be] lost."                 |
|                                                                              |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS    |
| LIMIT AND % WORST CASE OF CRITICAL MASS):  The equipment removed was only a  |
| part [of] the seal exhaust pump demister; therefore, a large mass is not     |
| anticipated.  The enrichment was at 3% in the form of UF4 with oil."         |
|                                                                              |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION  |
| OF THE FAILURES OR DEFICIENCIES:  NDA was not performed on seal demisters    |
| prior to removal.  The NDA is required to demonstrate that the component is  |
| less than a safe mass.  Spacing between components was maintained."          |
|                                                                              |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:  |
| At the direction of the [PSS,] the requirements for an NCS anomalous         |
| condition were initiated, and the [area was] boundaried off.  The filters    |
| removed will be scheduled to have NDA measurements performed."               |
|                                                                              |
| Portsmouth personnel stated that this event was a 4-hour notification        |
| because it involved a loss of one of two criticality controls without        |
| re-establishment within 4 hours.                                             |
|                                                                              |
| Portsmouth personnel notified the NRC resident inspector and the Department  |
| of Energy site representative.                                               |
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