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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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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)                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   39265       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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..      |
+------------------------------------------------------------------------------+