Event Notification Report for February 18, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/17/1999 - 02/18/1999
** EVENT NUMBERS **
35361 35373 35374 35375 35376 35377 35378 35379 35380 35381
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35361 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/10/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 11:19[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/10/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 07:00[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/17/1999|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |GARY SHEAR R3 |
| DOCKET: 0707002 |SCOTT MOORE NMSS |
+------------------------------------------------+FRANK CONGEL IRO |
| NRC NOTIFIED BY: ERIC SPAETH |BOB PIERSON NMSS |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| NRC BULLETIN 91-01, 4-HOUR NOTIFICATION INVOLVING INCORRECT RAFFINATE MASS |
| AND CONCENTRATION CALCULATION |
| |
| On 02/10/99, X-705 building personnel discovered that a Nuclear Criticality |
| Safety Approval (NCSA) requirement had not been maintained in the X-705 |
| Decontamination Facility. Uranium recovery waste stream solutions are |
| sampled to determine the U-235 concentration, mass, and enrichment as |
| spelled out in NCSA-0705_027, Heavy Metals Precipitation. These sample |
| results are used to calculate U-235 concentration and U-235 mass prior to |
| transferring and processing the waste solutions as identified in the |
| administrative requirements of the NCSA. |
| |
| Sample results for raffinate solutions (recovery waste streams) were |
| recorded incorrectly on the raffinate transfer sheet and the heavy metals |
| batch sheets. The double contingency principle was violated as result of: |
| 1) failure of the operator to correctly determine the U-235 concentration |
| prior to transfer (control "A") and 2) failure of supervision to find the |
| error while verifying the data and calculations (control "B"). This error |
| resulted in solution being transferred and processed to a geometrically |
| unfavorable sludge collection tub without the correct U-235 concentration |
| and U-235 mass being recorded. |
| |
| There was no loss of hazardous/radioactive material or radioactive |
| radiological contamination exposure as a result of this event. |
| |
| SAFETY SIGNIFICANCE OF EVENTS: The safety significance of this event is |
| low. This is because when this material was sampled for enrichment, the |
| enrichment was found to be 3.95% U-235. Also, due to the reduction of HEU |
| material on site, material now being processed through the heavy metals |
| systems routinely has an enrichment less than 10% U-235. |
| |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED (BRIEF SCENARIO[S] OF HOW |
| CRITICALITY COULD OCCUR): For a criticality to occur, both calculations of |
| how much material is in the system must be wrong and the total mass of |
| material must exceed 760 grams U-235. The minimum critical mass for 100% |
| enriched material is approximately 760 grams U-235. Even if the enrichment |
| had been 100%, the total mass in the system as a result of this event would |
| have been 245 grams. |
| |
| Also, a second path would be the processing material and collecting material |
| with greater than the minimum critical mass in the heavy metals collection |
| drums. |
| |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY. CONCENTRATION, ETC.): |
| The controlled parameter in this case was mass. (Both of the mass controls |
| were lost because the calculations were in error.) |
| |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS |
| LIMIT AND % WORST CASE OF CRITICAL MASS): The total amount of material in |
| the system was 245 grams U-235 assuming an enrichment of 100%. The |
| enrichment was measured after the event and found to be 3.95% U-235. The |
| material was uranium solution. The minimum critical mass at 100% enrichment |
| is approximately 760 grams U-235, and using the 100% enriched values, the |
| percent worst case critical mass is 32.2%. |
| |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION |
| OF THE FAILURES OR DEFICIENCIES: NCSA-0705_027 requires that material to be |
| processed through the heavy metals recovery system is sampled and the total |
| amount of uranium in the material calculated and recorded by an operator on |
| a transfer sheet and verified by another operator or supervisor on the same |
| sheet. If the enrichment of the sample is not known, an enrichment of 100% |
| is assumed for the calculation. The total amount of U-235 allowed to be |
| processed at any time is limited to 200 grams. The calculations done by |
| both the operator and the verifier used a concentration value ten times less |
| than the actual enrichment, which was only 3.95%. |
| |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED: |
| The heavy metals precipitation was shutdown and isolated. Similar |
| operations (microfiltration filter press and oil and grease removal unit ) |
| were also shut down and isolated. An investigation has been initiated to |
| determine if similar anomalous conditions exists in those operations. |
| |
| The NRC resident inspector has been informed of this event by the Portsmouth |
| personnel. |
| |
| *************** UPDATE AT 1825 ON 02/17/99 FROM JOE HALCOMB RECEIVED BY |
| TROCINE *************** |
| |
| On 02/10/99, the error in the mass values for the sludge collection drum was |
| corrected. This changed the total U-235 mass in the drum from 43.02 grams |
| to 139.78 grams. This value is below the NCSA limit of 200 grams. |
| |
| Portsmouth personnel notified the NRC resident inspector. The NRC |
| operations officer notified the R3DO (Jordan), NMSS EO (Haughney), and IRO |
| (Hogan). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35373 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 02/17/1999|
| UNIT: [] [2] [] STATE: NJ |NOTIFICATION TIME: 02:16[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/17/1999|
+------------------------------------------------+EVENT TIME: 02:02[EST]|
| NRC NOTIFIED BY: STEVE SAUER |LAST UPDATE DATE: 02/17/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP R1 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |98 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - TECH SPEC REQUIRED PLANT SHUTDOWN DUE TO A 28 VOLT DC BATTERY CELL TESTING |
| LOW - |
| |
| AT 0202 ON 02/17/99, DURING THE PERFORMANCE OF A QUARTERLY SURVEILLANCE |
| TEST, THE VOLTAGE OF ONE OF THE 28 VOLT DC BATTERY CELLS TESTED AT 2.11 VDC. |
| THE TECH SPEC MINIMUM LIMIT IS 2.13 VDC. TECH SPEC LCO A/S 3.8.2.5 REQUIRES |
| THE LICENSEE TO REPLACE THE AFFECTED CELL IN TWO HOURS OR PLACE UNIT 2 IN |
| THE HOT STANDBY MODE WITHIN SIX HOURS. THE LICENSEE PLANS TO REPLACE THE |
| AFFECTED CELL WITHIN TWO HOURS. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE AT 0354 ON 02/17/99 FROM STEVE SAUER TO JOLLIFFE * * * |
| |
| AT 0351 ON 02/17/99, THE LICENSEE REPLACED THE AFFECTED BATTERY CELL AND |
| EXITED TECH SPEC LCO A/S 3.8.2.5. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. THE NRC |
| OPERATIONS OFFICER NOTIFIED THE R1DO JIM TRAPP. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35374 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 02/17/1999|
| UNIT: [1] [2] [] STATE: PA |NOTIFICATION TIME: 03:50[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/17/1999|
+------------------------------------------------+EVENT TIME: 02:50[EST]|
| NRC NOTIFIED BY: CARL RICH |LAST UPDATE DATE: 02/17/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP 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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - PLANT SECURITY REPORT - |
| |
| A COMPROMISE OF PLANT SECURITY DOCUMENT WAS DISCOVERED. COMPENSATORY |
| MEASURES WERE IMMEDIATELY TAKEN UPON DISCOVERY. CONTACT THE NRC OPERATIONS |
| OFFICER FOR ADDITIONAL DETAILS. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35375 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 02/17/1999|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 05:16[EST]|
| RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 02/17/1999|
+------------------------------------------------+EVENT TIME: 00:20[CST]|
| NRC NOTIFIED BY: DARYL NOHR |LAST UPDATE DATE: 02/17/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN R3 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - UNIT 2 RECEIVED ESF ACTUATIONS DUE TO A FAILED VOLTAGE REGULATOR. - |
| |
| AT 0020 CST ON 02/17/99, UNIT 2 (100% POWER) UNEXPECTEDLY RECEIVED THE |
| FOLLOWING ENGINEERED SAFETY FEATURE (ESF) ACTUATIONS: HALF SCRAM SIGNAL, |
| HALF PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) GROUP 1 ISOLATION SIGNAL |
| (MAIN STEAM LINE VALVES), HALF PCIS GROUP 2 ISOLATION SIGNAL (VENT AND |
| SAMPLE VALVES INSIDE THE DRYWELL), AND REACTOR WATER CLEANUP ISOLATION |
| SIGNAL. AS PART OF THE PARTIAL PCIS GROUP 2 ESF ACTUATION, SEVERAL PRIMARY |
| CONTAINMENT ISOLATION VALVES CLOSED. |
| |
| AT THE TIME OF THE ESF ACTUATION, THE #2A REACTOR PROTECTION SYSTEM (RPS) |
| WAS BEING SUPPLIED FROM ITS RESERVE FEED, AND THE LICENSEE DETERMINED IT TO |
| BE TRIPPED DUE TO A FAILED VOLTAGE REGULATOR. THE LICENSEE REENERGIZED THE |
| #2A RPS FROM ITS NORMAL FEED AND RESTORED THE PLANT LINEUP TO NORMAL EXCEPT |
| THE #2A MAIN STEAM LINE RADIATION MONITOR DOWNSCALE WOULD NOT RESET. THE |
| LICENSEE INSERTED A HALF SCRAM SIGNAL AND A HALF PCIS GROUP 1 ISOLATION |
| SIGNAL IN ACCORDANCE WITH TECH SPEC REQUIREMENTS WHILE REPAIRS ARE IN |
| PROGRESS. |
| |
| THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35376 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 02/17/1999|
| UNIT: [1] [2] [] STATE: MI |NOTIFICATION TIME: 08:23[EST]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/16/1999|
+------------------------------------------------+EVENT TIME: 13:56[EST]|
| NRC NOTIFIED BY: MARY B. GREENDONNER |LAST UPDATE DATE: 02/17/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MIKE JORDAN R3 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N N 0 Cold Shutdown |0 Cold Shutdown |
|2 N N 0 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - FITNESS-FOR-DUTY REPORT - |
| |
| AT 1356 ON 02/16/99, A LICENSEE SUPERVISOR WAS DETERMINED TO BE UNDER THE |
| INFLUENCE OF ALCOHOL DURING A FOR-CAUSE FITNESS-FOR-DUTY TEST. THE |
| INDIVIDUAL'S PLANT ACCESS AUTHORIZATION WAS TERMINATED. THE INDIVIDUAL HAS |
| BEEN REFERRED TO THE LICENSEE FITNESS-FOR-DUTY PROGRAM. CONTACT THE NRC |
| OPERATIONS OFFICER FOR ADDITIONAL DETAILS. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 35377 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 02/17/1999|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 11:22[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 02/17/1999|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 09:52[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 02/17/1999|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |MIKE JORDAN R3 |
| DOCKET: 0707001 |SCOTT MOORE, NMSS EO |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BILL HALICKS | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAAA 20.1906(d) SURFACE CONTAMINATION E| |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - UF6 CYLINDER RECEIVED WITH REMOVABLE RADIOACTIVE SURFACE CONTAMINATION - |
| |
| AT 0952 CST ON 02/17/99, PADUCAH RECEIVED AN EMPTY UF6 CYLINDER ON THE BACK |
| OF A FLAT BED TRUCK FROM STARMET CMI, BARNWELL, SC. THE CARRIER WAS RSB |
| LOGISTICS, ST LOUIS, MO. THE SURFACE OF THE CYLINDER WAS SURVEYED UPON |
| RECEIPT AND CONTAMINATION LEVELS WERE 2,379 DPM PER 100 SQUARE CM BETA/GAMMA |
| REMOVABLE RADIOACTIVE SURFACE CONTAMINATION. (THE MAXIMUM ACCEPTABLE LIMIT |
| OF 10CFR71.87(i) IS 2,200.) THE SURVEY RESULTS OF THE TRUCK WERE LESS THAN |
| THE MINIMUM DETECTABLE ACTIVITY. THE LICENSEE PLACED THE CYLINDER IN A |
| RADIOLOGICALLY CONTROLLED AREA AND PLANS TO DECONTAMINATE IT. |
| |
| PADUCAH PERSONNEL NOTIFIED THE NRC REGION 3 IN ACCORDANCE WITH THE |
| REQUIREMENTS OF 10CFR20.1906(d)(1) AS A 1-HOUR EVENT NOTIFICATION REPORT. |
| PADUCAH PERSONNEL ALSO NOTIFIED THE NRC RESIDENT INSPECTOR.. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35378 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 02/17/1999|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 13:05[EST]|
| RXTYPE: [1] W-3-LP |EVENT DATE: 02/17/1999|
+------------------------------------------------+EVENT TIME: 12:19[EST]|
| NRC NOTIFIED BY: MARK PALMER |LAST UPDATE DATE: 02/17/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ANN BOLAND R2 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|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 |70 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED PLANT SHUTDOWN DUE TO FAILURE OF THE 'A' |
| REACTOR TRIP BREAKER TO CLOSE RELIABLY DURING TESTING |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "During [technical specification] surveillance testing [with the unit] at |
| 100% power, a testing failure occurred on the train 'A' reactor trip |
| breaker. The test in progress was MST-I001, Train 'A' Solid State |
| Protection System Actuation Logic and Master Relay Test. During this test, |
| the 'A' reactor trip breaker failed to close with the test pushbutton. The |
| following timeline occurred:" |
| |
| "0821- [The] train 'A' reactor trip bypass breaker [was racked in and |
| closed]. This began a 2-hour time |
| limit allowed for surveillance testing. |
| 0916 - Reactor trip breaker 'A' failed to close with the test pushbutton. |
| At this point, the 2-hour limit for |
| surveillance testing ended, and [Technical Specification] 3.3.1, action 8, |
| was entered. This action |
| required the plant to be in Mode 3 within 6 hours. The time to enter Mode 3 |
| is 1516. |
| 1026 - NRC Region II representative, George MacDonald, [was] notified of |
| [limiting condition for operation] |
| and necessity to be in Mode 3 by 1516. Mr. MacDonald was notified because |
| [the] Harris resident |
| inspectors are out of town. |
| 1219 - [A generator] load reduction for plant shutdown [was commenced]. |
| Maintenance and engineering |
| personnel are investigating the problem." |
| |
| The licensee emphasized that the train 'A' reactor trip breaker did not fail |
| to open, which is its safety function. The breaker only failed to re-close. |
| It has since been opened and re-closed several times during ongoing |
| troubleshooting activities. The licensee currently believes that the |
| failure of the breaker to re-close reliably may be the result of a possible |
| problem with the test circuitry allowing the test signal to stay in. |
| |
| Although all of the emergency diesel generators and emergency core cooling |
| systems are operable and available if needed, the licensee stated that the |
| emergency response date system is not available due to a Y2K problem. (The |
| Y2K problem is not related to the breaker problem.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35379 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 02/17/1999|
| UNIT: [1] [] [] STATE: MD |NOTIFICATION TIME: 15:55[EST]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 02/17/1999|
+------------------------------------------------+EVENT TIME: 14:30[EST]|
| NRC NOTIFIED BY: ERIC MEERBACH |LAST UPDATE DATE: 02/17/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION OF HIGH COLIFORM IN THE DRINKING WATER AT THE VISITOR'S |
| CENTER |
| |
| A positive coliform result was received for the drinking water at the site's |
| visitor's center. Accordingly, Chemistry personnel were notified, and an |
| Issue Report was generated. The licensee also notified the Maryland |
| Department of the Environment and the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Hospital |Event Number: 35380 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: LOWER BUCKS HOSPITAL |NOTIFICATION DATE: 02/17/1999|
|LICENSEE: LOWER BUCKS HOSPITAL |NOTIFICATION TIME: 16:24[EST]|
| CITY: BRISTOL REGION: 1 |EVENT DATE: 02/17/1999|
| COUNTY: BUCKS STATE: PA |EVENT TIME: 12:00[EST]|
|LICENSE#: SNM-1800 AGREEMENT: N |LAST UPDATE DATE: 02/17/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |JIM TRAPP R1 |
| |CHARLEY HAUGHNEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DR. MARK ANSLEY | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCAR CARDIAC PACEMAKER | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| DEATH OF A PATIENT WITH AN IMPLANTED NUCLEAR-POWERED CARDIAC PACEMAKER |
| (24-hour report) |
| |
| A representative from Lower Bucks Hospital located in Bristol, PA, reported |
| the death of a patient with an implanted nuclear-powered cardiac pacemaker. |
| The patient expired today (02/17/99) at Einstein Hospital located in |
| Philadelphia, PA. The pacemaker was manufactured by Coratomic (model |
| #C-101, serial #1054), and it contained 4 grams of Plutonium-238. |
| |
| The pacemaker is currently implanted in the patient, and the licensee plans |
| to have Einstein Hospital remove it. Once the pacemaker is retrieved, it |
| will be shipped to the manufacturer for proper disposal. When notification |
| of receipt is received by the licensee, the licensee plans to submit a |
| written report to the NRC. The licensee also plans to notify the NRC Region |
| I Office. |
| |
| (Contact the NRC operations officer for a site contact telephone number.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35381 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 02/17/1999|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 18:47[EST]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 02/17/1999|
+------------------------------------------------+EVENT TIME: 18:40[EST]|
| NRC NOTIFIED BY: JIM KRONENBITTER |LAST UPDATE DATE: 02/17/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JIM TRAPP R1 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | |
|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 |98 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED PLANT SHUTDOWN DUE TO FAILURE TO PERFORM |
| SURVEILLANCE TESTING IN ACCORDANCE WITH ASME SECTION XI REQUIREMENTS |
| FOLLOWING REPLACEMENT OF EMERGENCY (ISO) CONDENSER TUBE BUNDLES LAST FALL |
| |
| The following text is a portion of a facsimile received from the licensee: |
| |
| "In accordance with Technical Specification 3.2.6(a)1, Quality Group A, B, |
| and C components shall satisfy the requirements contained in Section XI of |
| the ASME Boiler and Pressure Vessel Code and applicable addenda for |
| continued service of ASME Code Class 1, 2, and 3 components to be considered |
| operable. The pre-service inspection (radiographs) for emergency condensers |
| 111, 112, 121, and 122 was performed prior to the construction hydrostatic |
| test for emergency condensers 111, 112, 121, and 122. This sequence of |
| testing is contrary to the requirements of the ASME code. Emergency |
| condensers 111, 112, 121, and 122 are inoperable. Technical Specification |
| 3.1.3(e) requires [that] a normal orderly shutdown shall be initiated within |
| [1-]hour and [that] the reactor shall be in the Cold Shutdown condition |
| within [10] hours with no emergency cooling system operable." |
| |
| The licensee stated that all of the Unit 1 emergency condensers were |
| declared inoperable at approximately 1750, and a unit shutdown was commenced |
| at 1840. |
| |
| The licensee notified the NRC resident inspector. |
| |
| HOO NOTE: At approximately 1900 on 02/17/99, the licensee requested a |
| Notice of Enforcement Discretion to |
| allow 48 hours to perform the required testing. A Notice of Enforcement |
| Discretion was granted by |
| the NRC Region 1 Office at 2026. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021