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 >2200�F 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 <2200�F) 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 | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| 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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021