Event Notification Report for January 13, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/12/1999 - 01/13/1999
** EVENT NUMBERS **
35243 35244 35245 35246 35247
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|Other Nuclear Material |Event Number: 35243 |
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| REP ORG: ROSEMOUNT NUCLEAR INST. |NOTIFICATION DATE: 01/12/1999|
|LICENSEE: ROSEMOUNT NUCLEAR INSTR. |NOTIFICATION TIME: 09:44[EST]|
| CITY: REGION: |EVENT DATE: 01/12/1999|
| COUNTY: STATE: |EVENT TIME: 09:44[EST]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 01/12/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GENE KELLY R1 |
| |LEN WERT R2 |
+------------------------------------------------+JIM GAVULA R3 |
| NRC NOTIFIED BY: Jeffery Schmitt |BLAIR SPITZBERG R4 |
| HQ OPS OFFICER: JOHN MacKINNON |Vern Hodge NRR |
+------------------------------------------------+ |
|EMERGENCY CLASS: | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| Notification under 10 CFR Part 21 for Rosemount Model-1153B Alphaline |
| Nuclear Pressure Transmitter |
| |
| Rosemounts Nuclear Instruments, Inc., (RNII) discovered two errors contained |
| in the Rosemount Specification and Outline Dimension Drawings for Model-1153 |
| Series-B Alphaline Nuclear Pressure Transmitters. The first error exists in |
| the Specification and Outline Dimension Drawings for all 1153 Series-B Model |
| types (refs. a - d). In each of these drawings, the module qualified life |
| and electronics qualified life shown in Figure 2 are in error. The graphs |
| of Qualified Life vs. Ambient Operating Temperature were incorrectly |
| transposed from ref. E in June of 1985. This error resulted in overstating |
| the qualified life of both the module and the electronics. Model-1153 |
| Series-B Qualification Report (ref. E), Product Data Sheet (ref. F), and |
| Product Manual (ref. G) are all correct, and the error is contained only in |
| the Specification and Outline Dimension Drawings. |
| |
| The second error exists only in the Specification and Outline Dimension |
| Drawings for Differential Pressure Transmitter, Model 1153DB (ref. b). In |
| paragraph 4.2.2, the accuracy of the output code "R" following to 22 |
| megarads TID of gamma radiation exposure is incorrectly stated as +/- 1.5% |
| of Upper Range Limit. The correct accuracy value should be +/- 4.0% of |
| Upper Range Limit following exposure to 22 megarads TID gamma radiation |
| exposure. This was a transposition error which occurred in the most recent |
| revision of ref. B on June 27, 1997. The Model-1153 Series-B Qualification |
| Report (ref. e), Product Data Sheet (ref. f), and Product Manual (ref. g) |
| were not affected by this error and are stated correctly. |
| |
| All affected specification drawings will be revised within 60 days to |
| reflect the correct qualified life vs. temperature relationships as well as |
| output code "R" accuracy. No further action related to this issue is |
| expected. |
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|Power Reactor |Event Number: 35244 |
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| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 01/12/1999|
| UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 11:09[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 01/12/1999|
+------------------------------------------------+EVENT TIME: 08:49[EST]|
| NRC NOTIFIED BY: DAVE FYRE |LAST UPDATE DATE: 01/12/1999|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: |GENE KELLY R1 |
|10 CFR SECTION: |JOHN DAVIDSON, IAT NMSS |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |ROBERT SKELTON, IAT NRR |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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 |
| | |
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EVENT TEXT
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| Offsite notification made to Maryland Department of Natural Resources |
| Division of Forestry due to fire on owners controlled area |
| |
| The licensee was informed at 0849 ET that they had a small fire in the owner |
| controlled area. The fire was extinguished by onsite personnel shortly after |
| the fire was discovered. The fire burned an area approximately 40' by 40'. |
| This is the fourth fire that has occurred in the owner controlled area in |
| the last several months. The licensee asked the Maryland Department of |
| Natural Resources Division of Forestry to investigate the cause of the |
| fire. |
| |
| The NRC resident inspector was notified of this event notification. |
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|Other Nuclear Material |Event Number: 35245 |
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| REP ORG: U.S. ARMY |NOTIFICATION DATE: 01/12/1999|
|LICENSEE: U.S. ARMY |NOTIFICATION TIME: 16:27[EST]|
| CITY: Anniston REGION: 2 |EVENT DATE: 01/12/1999|
| COUNTY: STATE: AL |EVENT TIME: [CST]|
|LICENSE#: 12-00722-06 AGREEMENT: Y |LAST UPDATE DATE: 01/12/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JIM GAVULA R3 |
| |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JEFF HAVENNER | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
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EVENT TEXT
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| SHIPMENT RECEIVED WITH EXCESSIVE SURFACE CONTAMINATION |
| |
| The U.S. Army made the following report in accordance with 10 CFR |
| 20.1906(d), after receiving a package with excessive external surface |
| contamination. The Anniston Army Depot received a package containing an |
| M1A1 collimator, which normally contains 10 Ci of tritium. The package had |
| been shipped from the USMC training facility in Twentynine Palms, CA, via an |
| undetermined carrier. |
| |
| Upon receipt of the package, employees of the Defense Logistics Agency |
| performed wipe tests of the package. These tests revealed that the surface |
| of the package was contaminated with an activity of 8,200 dpm/100 cm�. In |
| addition, some contamination was discovered inside of the hood where the |
| wipe tests were performed. The tritium source within the collimator appears |
| to be leaking. The U.S. Army is reviewing the shipping papers regarding |
| this package and has contacted NRC Region III (J. Cameron) regarding this |
| event. |
| |
| (Call the NRC Operations Center for a contact telephone number.) |
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|Fuel Cycle Facility |Event Number: 35246 |
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/12/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:18[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/12/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:20[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/12/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |JIM GAVULA R3 |
| DOCKET: 0707002 |JOHN SURMEIER NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC SPAETH | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
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EVENT TEXT
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| 4-HOUR NRC BULLETIN 91-01 REPORT |
| |
| THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PORTSMOUTH: |
| |
| "ON JANUARY 12, 1999, AT 1420 HOURS, THE NUCLEAR CRITICALITY SAFETY (NCS) |
| STAFF DETERMINED THAT SEVERAL NUCLEAR CRITICALITY SAFETY APPROVALS (NCSA) |
| FOR X-705 [DECONTAMINATION FACILITY], THAT DEAL WITH DISASSEMBLY OF |
| EQUIPMENT, WERE DEFICIENT. NCSA-0705.042, NCSA-0705.031, [AND] NCSA-0705.33 |
| WERE DEFICIENT IN THAT THEY FAILED TO IDENTIFY THE CONTROLS NECESSARY TO |
| ENSURE THAT THE DISASSEMBLY OF EQUIPMENT, PREVIOUSLY CLASSIFIED 'UH' |
| (UNCOMPLICATED HANDLING) BY GEOMETRY, DID NOT LEAD TO AN UNSAFE |
| CONFIGURATION FOR NCS. BUILDING AND NCS PERSONNEL HAVE ASSESSED THE AREA, |
| AND NO UNSAFE CONDITIONS OR DISASSEMBLY ACTIVITIES WERE FOUND." |
| |
| "SAFETY SIGNIFICANCE OF EVENTS: DURING DISASSEMBLY IF A PIECE OF EQUIPMENT |
| CLASSIFIED AS 'UH' BASED ON GEOMETRY, AN UNSAFE CONFIGURATION COULD OCCUR." |
| |
| "POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW |
| CRITICALITY COULD OCCUR): EQUIPMENT CLASSIFIED AS UH BY GEOMETRY, IF |
| DISASSEMBLED AND PLACED IN A PILE COULD RESULT IN AN UNSAFE CONFIGURATION." |
| |
| "CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY, CONCENTRATION, ETC.): |
| GEOMETRY IS THE PARAMETER OF CONCERN. HOWEVER, THIS CONTROL COULD BE LOST |
| DURING DISASSEMBLY OF THE EQUIPMENT." |
| |
| "ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE OF CRITICAL MASS): N/A - THE NCSAs WERE EVALUATED AT |
| 100 WT% ENRICHMENT WITH NO MASS RESTRICTIONS." |
| |
| "NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: THE NCSA/NCSE DID NOT ADEQUATELY CONSIDER |
| THE EFFECT OF DISASSEMBLY ON EQUIPMENT CLASSIFIED AS 'UH' BASED ON |
| GEOMETRY." |
| |
| "CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: |
| X-705 BUILDING MANAGEMENT HAVE DISCONTINUED DISASSEMBLY OPERATIONS OF |
| EQUIPMENT INVOLVING COMPONENTS PREVIOUSLY CLASSIFIED AS 'UH' BY GEOMETRY. |
| APPLICABLE NCSA/NCSEs WILL BE CORRECTED AND IMPLEMENTED." |
| |
| "THERE WAS ON LOSS OF HAZARDOUS/RADIOACTIVE MATERIAL OR |
| RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT." |
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|Power Reactor |Event Number: 35247 |
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| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 01/13/1999|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 01:21[EST]|
| RXTYPE: [1] GE-6 |EVENT DATE: 01/13/1999|
+------------------------------------------------+EVENT TIME: 00:30[CST]|
| NRC NOTIFIED BY: RILEY COLLINS |LAST UPDATE DATE: 01/13/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BLAIR SPITZBERG R4 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|NLCO TECH SPEC LCO A/S | |
| | |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| PLANNED SHUTDOWN DUE TO INDICATIONS OF DEGRADATION ON THE DIVISION I DIESEL |
| GENERATOR OUTPUT BREAKER CURRENT TRANSFORMERS |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "[During a planned maintenance outage, it was discovered that the] Division |
| I diesel generator output breaker current transformers (CT) have indications |
| of degradation. [A small puddle of CT encapsulant material was noticed on |
| the cubicle floor when the breaker cubicle was opened.] This degradation is |
| suspected to be related to a [10 CFR] Part 21 report from ABB Power |
| Distribution, Inc., on CT encapsulant material dated April 17, 1989. The |
| [Division] I [diesel generator] is currently inoperable. For personnel |
| protection, it is necessary to shut down the unit to complete inspection and |
| repair. The unit is shutting down prior to the [technical specification] |
| time limit, and [the unit] is not currently in the shutdown action |
| statement." |
| |
| At the time of this notification, the unit was approximately 24 - 25 hours |
| into a 72-hour limiting condition for operation for planned diesel generator |
| maintenance activities. The unit shutdown is tentatively planned to |
| commence at 0030 on 01/13/99. The licensee expects that the unit will enter |
| Mode 3 (Hot Shutdown) some time on day shift, and the licensee plans to |
| place the unit in Mode 4 (Cold Shutdown). The current estimated restart |
| date is 01/19/99. |
| |
| At this time, the licensee does not believe that this issue affects the |
| other diesel generator because surveillance tests were successfully |
| completed on it last week. However, the impact on the other diesel |
| generator is still being evaluated. |
| |
| The licensee notified the NRC resident inspector. |
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