Event Notification Report for October 11, 2002
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/10/2002 - 10/11/2002
** EVENT NUMBERS **
39199 39265 39266 39267 39268
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 39199 |
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| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 09/18/2002|
| UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 17:10[EDT]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 09/17/2002|
+------------------------------------------------+EVENT TIME: 16:52[MST]|
| NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 10/10/2002|
| HQ OPS OFFICER: RICH LAURA +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DAVE LOVELESS R4 |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 99 Power Operation |99 Power Operation |
|2 N Y 98 Power Operation |98 Power Operation |
|3 N Y 99.6 Power Operation |99.6 Power Operation |
+------------------------------------------------------------------------------+
EVENT TEXT
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| HEAT BALANCE CALCULATION ERROR ON REACTOR POWER |
| |
| "The following event description is based on information currently |
| available. It through subsequent reviews of this event, additional |
| information is identified that Is pertinent to this event or alters the |
| information being provided at this time, a follow-up notification will be |
| made via the ENS or under the reporting requirements of 10CFR50.73. |
| |
| "Palo Verde Nuclear Generating Station Units 1, 2, and 3 are evaluating the |
| potential that the Maximum Power Level of 3876 megawatts thermal (100% |
| power), specified in Operating License Condition 2.C(1) may have been |
| exceeded in the past due to an unconservative value of reactor coolant pump |
| (RCP) heat in the secondary calorimetric calculation since initial plant |
| operation. The value of total energy input due to RCP operation used in the |
| calorimetric is 29.53 megawatts (MW) in Unit 1, 29.61 MW in Unit 2 and |
| 31.88 MW In Unit 3. Conservative engineering calculation of actual RCP heat |
| input based on electrical load is as low as 24.72 MW. Similarly, |
| conservative engineering calculation of actual RCP heat input based on fluid |
| power (pump differential pressure) is as low as 22.86 MW. Thus, the |
| calorimetric error may be as large as (31.88-22.86) 9.02 MW or approximately |
| 0.23%. |
| |
| "The error could have resulted in core power levels above the Operating |
| License limit of 3876 MW thermal. Due to current operating limitations on |
| reactor coolant system hot leg temperature, none of the Palo Verde units are |
| presently exceeding the licensed power limit. Unit 1 is at approximately 99% |
| power (3837 MW thermal, 39 MW margin). Unit 2 is at approximately 98% power |
| (3798 MW thermal, 78 MW margin). Unit 3 is at approximately 99.6% power |
| (3861 MW thermal, 15 MW margin) |
| |
| "This report is being made because a review of historical operating data may |
| reveal that the Maximum Power Level was exceeded. |
| |
| "The Palo Verde safety analyses bound a power level of 102%, thus the Units |
| remain within the safety analyses. As a compensatory measure, the station |
| has established an administrative limit of 99.75% power pending resolution |
| of this issue. |
| |
| "No ESF actuations occurred and none were required. There were no |
| structures, systems, or components that were inoperable at the time of |
| discovery that contributed to this condition. There were no failures that |
| rendered a train of a safety system inoperable and no failures of components |
| with multiple functions were involved. The event did not result in the |
| release of radioactivity to the environment and did not adversely affect the |
| safe operation of the plant or health and safety of the public." |
| |
| The NRC Resident Inspector has been notified. |
| |
| * * * RETRACTION FROM DANIEL HAUTALA ON OCTOBER 10, 2002 AT 1534 EDT TO MIKE |
| RIPLEY * * * |
| |
| "The following event description is based on information currently |
| available. If through subsequent reviews or this event, additional |
| information is identified that is pertinent to this event or alters the |
| information being provided at this time, a follow-up notification will be |
| made via the ENS or under the reporting requirements of 10CFR50.73. |
| |
| "This notification is a retraction to the September 17, 2002, ENS #39199 |
| which reported a calorimetric input error that could have resulted in core |
| power levels above the Operating License limit of 3876 MW thermal at Palo |
| Verde Nuclear Generating Station Units 1, 2, and 3. Further evaluation of |
| the calorimetric power calculation indicated the installed values were |
| conservative and no correction is required. |
| |
| "The NRC Resident Inspector has been notified." |
| |
| Notified R4 DO (William Jones) |
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|Power Reactor |Event Number: 39265 |
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| FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 10/10/2002|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 00:20[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/10/2002|
+------------------------------------------------+EVENT TIME: 00:08[EDT]|
| NRC NOTIFIED BY: ROBERT BOESCH |LAST UPDATE DATE: 10/10/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN WHITE R1 |
|10 CFR SECTION: | |
|ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
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| TECH SPEC REQUIRED SHUTDOWN DUE TO FAILURE TO MEET 2 OFFSITE POWER SUPPLIES |
| |
| "Susquehanna Unit 1 initiated a Technical Specification required shutdown |
| due to failure to meet LCO 3.8.1 Action A.3 and the Notice of Enforcement |
| Discretion (Docket No. 50-387), for operating with one inoperable offsite |
| power supply. The offsite power supply was originally lost due to a |
| Transformer failure on 10/3/02 at 0230 est. The NOED allowed Unit One to |
| continue operation until 10/1 0/02 at 0230. The shutdown requirements of LCO |
| 3.8.1 Action F (Mode 3 within 12 hours and Mode 4 within 36 hours) are being |
| implemented. It has been determined that replacement activities of the |
| transformer will not be completed in time to meet the NOED, and therefore |
| shutdown of unit 1 has been initiated as of 0008. |
| |
| "This event is a Technical Specification required shutdown, and is |
| reportable as a four hour ENS Notification under 10 CFR 50.72(b)(2)(I)." |
| |
| The Licensee has notified the NRC Resident Inspector. |
| |
| ***UPDATE 1113 EDT 10/10/02 ART FITCH TO MIKE NORRIS*** |
| |
| "At 09:35 hours on 10/10/2002 transformer T-20 was successfully connected to |
| start-up bus 20 restoring the second offsite power source. This allowed Unit |
| 1 to exit LCO 3.8.1 Action F and LCO 3.8.1 Action A.3 and the Notice of |
| Enforcement Discretion (Docket No. 50-387). Power reduction was halted at |
| 31% and plans are currently underway to restore Unit 1 to 100% power. |
| |
| "Unit 2 continues in Mode 4." |
| |
| The Licensee has notified the NRC Resident Inspector and plans a press |
| release. |
| |
| Notified R1DO (White). |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39266 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 10/10/2002|
| UNIT: [1] [2] [] STATE: MD |NOTIFICATION TIME: 10:29[EDT]|
| RXTYPE: [1] CE,[2] CE |EVENT DATE: 10/10/2002|
+------------------------------------------------+EVENT TIME: 09:45[EDT]|
| NRC NOTIFIED BY: JAMES GROOMS |LAST UPDATE DATE: 10/10/2002|
| HQ OPS OFFICER: MIKE NORRIS +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN WHITE R1 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) 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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| 4 HOUR OFFSITE NOTIFICATION TO MD DEPARTMENT OF ENVIRONMENT |
| |
| A sample of drinking water taken during a routine test come up positive for |
| Coliform(which is a bacteria). The levels are still low enough as not to |
| preclude the use of this water for drinking. The licensee has contacted the |
| MD Department of Environment to take and test additional samples. |
| |
| The licensee has notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 39267 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 10/10/2002|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 23:08[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/10/2002|
+------------------------------------------------+EVENT TIME: 20:16[EDT]|
| NRC NOTIFIED BY: ROBERT MELTON |LAST UPDATE DATE: 10/10/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |JOHN WHITE R1 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 20 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AUXILIARY FEEDWATER START ON PLANNED MANUAL REACTOR TRIP |
| |
| THIS 8 HOUR NOTIFICATION IS BEING MADE TO REPORT THAT SALEM UNIT 1 HAD |
| EXPERIENCED A 13 AUXILIARY FEED WATER PUMP AUTO START. THIS AUTO START |
| OCCURRED FOLLOWING A PLANNED MANUAL REACTOR TRIP FOR A SHUTDOWN FOR |
| REFUELING. 11 & 12 AFW PUMPS WERE STARTED MANUALLY PRIOR TO THE TRIP PER |
| PROCEDURE. THE 13 AFW PUMP STARTED POST TRIP DUE TO VALID STEAM GENERATOR |
| LOW LEVELS WHICH ARE EXPECTED ON A REACTOR TRIP. THE STEAM GENERATOR LOW |
| LEVEL AUTO START SET POINT WAS RAISED FROM 9% TO 14% EARLIER THIS YEAR BASED |
| ON INDUSTRY EVENTS. THIS MADE THE 13 AFW PUMP AUTO START MORE LIKELY DURING |
| A PLANT TRIP. |
| POST TRIP MAIN FEEDWATER TO THE STEAM GENERATORS WAS ISOLATED DUE TO THE |
| 'FEED WATER INTERLOCK' WHICH IS EXPECTED WITH A REACTOR TRIP. 13 AFW PUMP |
| HAS BEEN SHUTDOWN BY PROCEDURE SINCE 11 & 12 AFW PUMPS ARE MAINTAINING |
| ADEQUATE FEED FLOW. SALEM UNIT 1 IS CURRENTLY IN MODE 3. REACTOR COOLANT |
| SYSTEM TEMPERATURE IS 547 DEGREES (F) WITH PRESSURE AT 2235 PSIG. THERE WERE |
| TWO SHUT DOWN TECHNICAL SPECIFICATIONS IN EFFECT PRIOR TO THE TRIP; ONE |
| ASSOCIATED WITH THE 11 & 12 AFW PUMPS INOPERABLE BY PROCEDURE DUE TO THEIR |
| FLOW CONTROL VALVES BEING CLOSED PRIOR TO THE MANUAL REACTOR TRIP. THE |
| SECOND SHUT DOWN TECHNICAL SPECIFICATION IN EFFECT WAS ASSOCIATED WITH THE |
| 13 CONTAINMENT FAN COIL UNIT WHICH WAS TAGGED FOR REPAIR OF A LEAK. THE 11 & |
| 12 AFW PUMPS ARE NOW OPERABLE. THE FOLLOWING MAJOR SECONDARY EQUIPMENT WAS |
| TAGGED FOR MAINTENANCE: 13A CIRCULATING WATER PUMP, 12 HEATER DRAIN PUMP AND |
| 11 CONDENSATE PUMP. |
| |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 39268 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 10/10/2002|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 23:10[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/10/2002|
+------------------------------------------------+EVENT TIME: 22:22[EDT]|
| NRC NOTIFIED BY: GARY BRINSON |LAST UPDATE DATE: 10/10/2002|
| HQ OPS OFFICER: GERRY WAIG +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |GEORGE MCDONALD R2 |
|10 CFR SECTION: | |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 M/R Y 50 Power Operation |0 Hot Shutdown |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| RECEIVED A GROUP II ISOLATION DURING A PLANNED REACTOR SCRAM |
| |
| "Inserted Manual Scram for planned outage. Received a Group II isolation |
| (containment isolation valves) on RWL [less than] 3". Lowest indication |
| level -10". Group II isolation confirmed by STA." Plant shutdown to replace |
| 3 SRVs. All system operate properly. |
| |
| The NRC Resident Inspector was notified of this event by the licensee.. |
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