Event Notification Report for September 10, 1999
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/09/1999 - 09/10/1999
** EVENT NUMBERS **
36029 36037 36078 36139 36140 36141 36142
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|Power Reactor |Event Number: 36029 |
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+------------------------------------------------------------------------------+
| FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 08/13/1999|
| UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 18:18[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-L|EVENT DATE: 08/13/1999|
+------------------------------------------------+EVENT TIME: 17:28[EDT]|
| NRC NOTIFIED BY: MIKE HILL |LAST UPDATE DATE: 09/09/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES OGLE R2 |
|10 CFR SECTION: |JOSE CALVO NRR |
|ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |FRANK CONGEL IRO |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |99 Power Operation |
|2 N Y 100 Power Operation |99 Power Operation |
|3 N Y 100 Power Operation |99 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| -TS REQD SHUTDOWN OF ALL 3 UNITS DUE TO BOTH CONTROL ROOM VENT SYSTEM |
| CHILLERS INOP |
| |
| UNIT 1 AND UNIT 2 CONTROL ROOMS SHARE A COMMON VENTILATION SYSTEM; UNIT 3 |
| CONTROL ROOM HAS ITS OWN VENTILATION SYSTEM. TWO CHILLERS SERVE THE |
| VENTILATION SYSTEMS FOR ALL THREE CONTROL ROOMS. |
| |
| AT 1659 ON 08/13/99, THE 'B' TRAIN CONTROL ROOM CHILLER TRIPPED DURING |
| MAINTENANCE ACTIVITIES. TECH SPEC 3.7.16 REQUIRES THE LICENSEE TO RESTORE |
| THE INOPERABLE CHILLER TO OPERABLE STATUS WITHIN 30 DAYS OR SHUT ALL THREE |
| UNITS DOWN. |
| |
| AT 1728 ON 08/13/99, THE 'A' TRAIN CONTROL ROOM CHILLER ALSO TRIPPED DURING |
| MAINTENANCE ACTIVITIES. TECH SPEC 3.0.3 REQUIRES THE LICENSEE TO START |
| SHUTTING ALL THREE UNITS DOWN WITHIN ONE HOUR AND PLACE ALL THREE UNITS IN |
| MODE 3 WITHIN 12 HOURS WITH BOTH CONTROL ROOM VENTILATION SYSTEM CHILLERS |
| INOPERABLE. |
| |
| THE LICENSEE IS REDUCING THE POWER OF ALL THREE UNITS AT THE RATE OF 1% PER |
| HOUR AND IS ATTEMPTING TO RESTORE AT LEAST ONE CHILLER TO OPERABLE STATUS. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE AT 2336 ON 08/13/99 FROM SCOTT BATSON TO JOLLIFFE * * * |
| |
| AT 2240, THE LICENSEE RESTORED THE 'B' CHILLER TO OPERABLE STATUS USING THE |
| 'A' PUMP AND EXITED TS 3.0.3. TS 3.7.16 REMAINS IN EFFECT FOR THE 'A' |
| CHILLER. THE LICENSEE PLANS TO INCREASE POWER FROM A LOW LEVEL OF 87% AND |
| HAS INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS OFFICER |
| NOTIFIED THE R2DO CHUCK OGLE. |
| |
| *** UPDATE AT 1513 ON 9/9/99 FROM TODD TO POERTNER. *** |
| |
| The following is a portion of a facsimile received from the licensee: |
| "This event was initially reported due to initiation of shutdown of all |
| three Oconee units in accordance with Tech Specs. After all three units |
| reached approximately 85% rated power, the Tech Spec condition was exited. |
| The shutdown was terminated and the units returned to full power. After |
| further review, Duke Energy Company feels that the entry into the Tech Spec |
| condition which required shutdown was INVALID, for reasons explained below. |
| Because the units did actually initiate shutdown under the declared Tech |
| Spec condition, Duke Energy Company does not consider it appropriate to |
| retract the notification but is providing this update to indicate that the |
| conditions did not meet other reportability requirements of 10 CFR 50.72 or |
| 50.73." |
| |
| "This event was reported due to initiation of shutdown of all three Oconee |
| units in accordance with Tech Spec 3.7.16, Condition E, which requires entry |
| into Tech Spec 3.0.3 when two trains of the Chilled Water (WC) system are |
| inoperable. The WC system provides chilled water for the Control Room |
| Ventilation System on all three Oconee Units. Both the 'A' and 'B' chillers |
| had tripped when the initial report was made." |
| |
| "The 'B' chiller was successfully restarted in combination with the 'A' |
| chilled water pump. Based on this, one train of WC was declared operable. |
| Tech Spec 3.0.3 and 3.7.16, Condition E were exited. Tech Spec 3.7.16 |
| Condition B remained in effect. The shutdown of the Oconee units was |
| terminated. An update notification containing this information was made at |
| 2336 hours on 8-13-99." |
| |
| "Subsequently, troubleshooting found that the 'B' Chilled Water pump tripped |
| due to a faulty relay, which caused the 'B' Chiller trip. The 'A' Chiller |
| was inoperable due to inadequate refrigerant charge combined with excess |
| oil. Both the 'B' Chilled Water pump and the 'A' Chiller were repaired and |
| returned to service allowing Tech Spec 3.7.16, Condition B to be exited on |
| 8-17-99." |
| |
| "An Operability Evaluation concluded that the combination of 'A' Chilled |
| Water pump with the 'B' Chiller was Operable throughout the event. This |
| conclusion is based on the following facts: |
| |
| 1) The Oconee Chilled Water system was designed as a non-safety system. |
| 2) Operation following a Design Basis Event requires manual alignment and |
| restart. |
| 3) Restart is not required for an extended period (greater than 18 hours). |
| 4) Operation in this alignment is included in the applicable procedure. |
| 5) No maintenance was required on either the 'A' WC pump or the 'B' |
| Chiller. |
| |
| Therefore, the entry into Tech Spec 3.7.16, Condition E, and 3.0.3 was |
| invalid." |
| |
| "Also, the Operability Evaluation found that the 'A' chiller had been |
| confirmed to be operable on 7-27-99 when it was run as part of a post |
| maintenance test following PM of the 'A' Chilled Water Pump. The Operability |
| Evaluation concluded that the 'A' Chiller became inoperable after that date. |
| Therefore, the 30 day action statement of Tech Spec 3.7.16, Condition B for |
| one WC train out of service was not exceeded." |
| |
| "As a result of this Operability Evaluation, Duke Energy has concluded that |
| there are no conditions reportable under 50.73 associated with this event." |
| |
| The NRC resident inspector has been notified. |
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|Power Reactor |Event Number: 36037 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 08/18/1999|
| UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 09:00[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 08/17/1999|
+------------------------------------------------+EVENT TIME: 09:10[EDT]|
| NRC NOTIFIED BY: BOB KIDDER |LAST UPDATE DATE: 09/09/1999|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |BRENT CLAYTON R3 |
|10 CFR SECTION: |FEMA, DOE, USDA, HHS FAX |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |EPA, DOT (VIA NRC) FAX |
|NLTR LICENSEE 24 HR REPORT | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| RELEASE OF CHLORINATED WATER TO STORM DRAIN AND OFFSITE NOTIFICATION |
| |
| The licensee discovered that, due to valve leakage, a small amount of |
| chlorine was released to a storm drain. The following information was |
| submitted to the NRC Operations Center by facsimile: |
| |
| "The service water backwash valve on strainer 'd' was experiencing severe |
| leakage past the valve. The system engineer estimated approximately 200 gpm |
| leakage occurred. During this time, the system chlorination evolution |
| occurred for 40 minutes. The forebay water was treated to a concentration of |
| 1 ppm. The result is that an estimated 0.067 lbs of chlorine was discharged |
| to the storm drain. The reportable quantity for chlorine is 10 lbs. There is |
| no reportability requirement for CERCLA; however, an NPDES noncompliance did |
| occur. Reportability is being investigated. The strainer valve has been |
| isolated to prevent it from operating until repairs are complete." |
| |
| This event is reportable to the NRC within 24 hours in accordance with |
| Section 4.1 of the site Environmental Protection Plan. In addition, the |
| licensee is notifying the US EPA of this release. The NRC resident inspector |
| has been informed of this notification. |
| |
| * * * UPDATE 0942 9/9/1999 FROM SANFORD TAKEN BY STRANSKY * * * |
| |
| "On 8/17/99, the Perry Nuclear Power Plant (PNPP) discharged an estimated |
| 0.067 pounds of chlorine to a storm drain from the Service Water System. The |
| storm drain is not an acceptable discharge path for treated Service Water |
| per the National Pollution Discharge Elimination System (NPDES) permit. On |
| 8/18/99, the Ohio Environmental Protection Agency (EPA) was notified of the |
| chlorine discharge to the storm drain. Subsequently, an NRC notification was |
| made in accordance with 10CFR50.72(b)(2)(vi) for notification of other |
| government agencies (i.e., Ohio EPA). This notification also included a 24 |
| hour report in accordance with the EPP for an event that could result in |
| significant environmental Impact. The EPP report was conservatively made |
| since the environmental impact had not been fully evaluated. |
| |
| "The EPP requires, in part, that any occurrence of an unusual or important |
| event that indicates or could result in significant environmental impact |
| causally related to plant operations shall be recorded and reported to the |
| NRC within 24 hours with a written report submitted within 30 days. The site |
| environmentalist's evaluation determined that the chlorine content in the |
| service water was extremely low (1 ppm using the most conservative estimate) |
| and there was no significant effect or impact on the environment. Therefore, |
| the EPP reporting was not required and a written report will not be |
| submitted. The NRC notification per 10CFR50.72 is not affected by this |
| update." |
| |
| The NRC resident inspector has been informed of this update. Notified R3DO |
| (Phillips). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36078 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 08/27/1999|
| UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 02:10[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/26/1999|
+------------------------------------------------+EVENT TIME: 22:30[CDT]|
| NRC NOTIFIED BY: TROY LEAF |LAST UPDATE DATE: 09/09/1999|
| HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MELVYN LEACH R3 |
|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
+------------------------------------------------------------------------------+
| SAFEGUARDS SYSTEM DEGRADATION RELATED TO POWER SUPPLY FUNCTIONS |
| |
| At 0030 CDT on 08/27/99, it was determined that a security event which |
| occurred at 2230 CDT on 08/26/99 met the reportability requirements of 10 |
| CFR 73.71(b), Part 73, Appendix G, paragraph 1(c). The event involved a |
| safeguards system degradation related to power supply functions. |
| Compensatory measures were taken upon discovery. (Contact the NRC |
| operations officer for additional details and for a site contact telephone |
| number.) |
| |
| The licensee plans to notify the NRC resident inspector. |
| |
| * * * RETRACTION 1133 9/9/1999 FROM SWANSON TAKEN BY STRANSKY * * * |
| |
| The degradation reported in the initial notification does not meet the |
| reportability requirements of 10 CFR 73.71, and this notification has been |
| retracted. The NRC resident inspector has been informed of this retraction |
| by the licensee. Notified R3DO (Phillips). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36139 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 09/08/1999|
| UNIT: [3] [4] [] STATE: FL |NOTIFICATION TIME: 23:12[EDT]|
| RXTYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 09/08/1999|
+------------------------------------------------+EVENT TIME: 22:30[EDT]|
| NRC NOTIFIED BY: ANDRE DALL'AU |LAST UPDATE DATE: 09/09/1999|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT HAAG R2 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
|4 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH UNITS EXPERIENCED A TEMPORARY LOSS OF THE EMERGENCY RESPONSE DATA |
| SYSTEM. |
| |
| "DISCOVERED @ 2230 ERDADS AND ERDS STOPPED UPDATING DATA @ 2200. ERDS |
| CALLED OUT OF SERVICE AND TROUBLESHOOTING UNDERWAY TO DETERMINE CAUSE. |
| UNKNOWN AT THIS TIME IF FAILURE ASSOCIATED WITH Y2K. SYSTEM STARTED |
| UPDATING DUE TO TROUBLESHOOTING ACTIVITIES @ 2305." |
| |
| THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE 0313 9/9/1999 FROM DALL'AU TAKEN BY STRANSKY * * * |
| |
| "ERDS and ERDADS powered and declared functional at 2330 9/8/99. All |
| troubleshooting and testing complete with ERDS and ERDADS declared back in |
| service at 0250 9/9/99. Intermittent disk failures of the primary computer, |
| not any Y2K related failures, were determined to be the cause of the loss of |
| data." |
| |
| The NRC resident inspector will be informed of this update. Notified R2DO |
| (Haag). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36140 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 09/09/1999|
| UNIT: [1] [] [] STATE: MS |NOTIFICATION TIME: 14:45[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 09/09/1999|
+------------------------------------------------+EVENT TIME: 11:48[CDT]|
| NRC NOTIFIED BY: ERNEST MATHES |LAST UPDATE DATE: 09/09/1999|
| HQ OPS OFFICER: WILLIAM POERTNER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |GARY SANBORN R4 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| DIVISION III EMERGENCY DIESEL GENERATOR (EDG) FAILURE. |
| |
| The division III EDG was emergency stopped during a 24 hour surveillance |
| run. Preliminary indications are that the generator bearing failed as |
| indicated by high bearing temperature and sparks from the generator area |
| just prior to emergency stopping the EDG. The diesel was started at 1055 |
| CDT and secured at 1148 CDT. The licensee is investigating the cause of |
| the failure. |
| |
| The NRC resident inspector has been notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 36141 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: DC FABRICATORS |NOTIFICATION DATE: 09/09/1999|
|LICENSEE: DC FABRICATORS |NOTIFICATION TIME: 15:30[EDT]|
| CITY: FLORENCE REGION: 1 |EVENT DATE: 09/09/1999|
| COUNTY: STATE: NJ |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 09/09/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |TOM MOSLAK R1 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+GARY SANBORN R4 |
| NRC NOTIFIED BY: DONALD BRAMBLE | |
| HQ OPS OFFICER: WILLIAM POERTNER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| ALLOY IDENTIFICATION INSTRUMENT LOST DURING SHIPMENT |
| |
| On March 14, 1999, DC Fabricators shipped a small alloy identification |
| instrument to Texas Nuclear Technology via UPS. In early August, DC |
| Fabricators determined that the instrument had not arrived at Texas Nuclear |
| Technology. The device contains 45 millicuries of Fe-55 and 4 millicuries |
| of Cd-109. UPS is looking for the device but has been unable to locate it |
| to date. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36142 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: KANSAS DEPT OF HEALTH |NOTIFICATION DATE: 09/09/1999|
|LICENSEE: UNIVERSITY OF KANSAS MEDICAL CENTER |NOTIFICATION TIME: 17:33[EDT]|
| CITY: KANSAS CITY REGION: 4 |EVENT DATE: 09/08/1999|
| COUNTY: STATE: KS |EVENT TIME: 11:45[CDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 09/09/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GARY SANBORN R4 |
| |JOSIE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: RONALD FRASS (FAX) | |
| HQ OPS OFFICER: WILLIAM POERTNER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| POTENTIAL MEDICAL MISADMINISTRATION. |
| |
| A patient was administered 5.4 millicuries of Indium-111. The patient was |
| supposed to receive a dose of Chromium-51 for a blood volume test. The |
| preliminary investigation indicates a dose of 14 rads (cGy) to the spleen |
| and less than 5 rads whole body. The University of Kansas Medical Center |
| (KUMC) RSO was not available when the potential misadministration occurred, |
| and informed the Kansas Department Of Health And Environment (KDHE) upon her |
| return to the office. The KDHE and KUMC investigations have commenced. At |
| this time, KUMC has no further information regarding this event. |
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