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Event Notification Report for January 12, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/11/2001 - 01/12/2001

                              ** EVENT NUMBERS **

37613  37627  37659  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37613       |
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| FACILITY: SALEM                    REGION:  1  |NOTIFICATION DATE: 12/18/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 09:52[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        12/18/2000|
+------------------------------------------------+EVENT TIME:        06:40[EST]|
| NRC NOTIFIED BY:  RUSS GUMBERT                 |LAST UPDATE DATE:  01/11/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN WHITE           R1      |
|10 CFR SECTION:                                 |                             |
|AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| CONTAINMENT FAN COOLER UNITS DECLARED INOPERABLE                             |
|                                                                              |
| "At 0640 on 12/18/00, '11' service water accumulator was declared inoperable |
| based on water level low out of specification for Technical Specifications.  |
| This condition was identified following calibration of the 'B' level device. |
| The service water accumulators support containment integrity by ensuring the |
| containment fan coils remain properly filled during a design basis accident. |
| Tech Spec 3.6.1.1 and Tech Spec 3.6.2.3 were entered for containment         |
| integrity and '11' and '12' containment fan coil unit inoperability. Actions |
| were taken within one hour to comply with containment integrity Tech Spec.   |
| The service water accumulator was filled to within specification at 0713 at  |
| which time Tech Spec 3.6.1.1 was exited. The '11' and '12' containment fan   |
| coil units were restored to operable at 0744 and Tech Spec 3.6.2.3 was       |
| exited. Actions are underway to calibrate the 'A' channel of level           |
| indication. All power plant parameters remained stable throughout the event  |
| and no other safety systems were affected."                                  |
|                                                                              |
| The NRC resident inspector will be informed of this notification by the      |
| licensee.                                                                    |
|                                                                              |
| * * * UPDATE 1312EST ON 1/11/01 FROM BENSON BINGGELI TO S. SANDIN * * *      |
|                                                                              |
| The licensee is retracting this report based on the following:               |
|                                                                              |
| "On December 18, 2000, a four-hour report was made for Salem Unit 1 in       |
| accordance with 10CFR50.72(B) (2) (iii) due to the water level for the 11    |
| Service Water accumulator being out of specification low based on readings   |
| from the 'B' level device. The service water accumulators support            |
| containment integrity by ensuring the containment fan coils remain properly  |
| filled during a design basis accident.                                       |
|                                                                              |
| "There are two level devices, 'A' and 'B', associated with each SW           |
| accumulator. During the time that the 'B' level device indicated that the SW |
| accumulator was out of specification, the 'A' level device continued to show |
| that the accumulator level was within the required level specification.      |
|                                                                              |
| "Following the calibration of the 'B' level device which showed that level   |
| on the 'B' channel was reading low out                                       |
| of specification, M&TE equipment (differential pressure gauge) was connected |
| to the 11 SW accumulator to provide an independent reading of the tank       |
| level. The M&TE equipment confirmed that the 11 SW accumulator level was     |
| within 0.5 inches of the level indicated by the 'A' level device. Based on   |
| this confirmation, the 'A' level device on the 11 SW accumulator is          |
| providing  an accurate indication of level in the tank.                      |
|                                                                              |
| "Since the 'A' level device readings were within the required Technical      |
| Specification level band for the 11 SW accumulator, the 11 SW accumulator    |
| was always operable and capable of performing its design basis function.     |
| Based on this information, the 4-hour report is being retracted."            |
|                                                                              |
| The licensee will inform the NRC resident inspector.  Notified R1DO(Lew).    |
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!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|Power Reactor                                    |Event Number:   37627       |
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| FACILITY: BRUNSWICK                REGION:  2  |NOTIFICATION DATE: 12/20/2000|
|    UNIT:  [] [2] []                 STATE:  NC |NOTIFICATION TIME: 22:58[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        12/20/2000|
+------------------------------------------------+EVENT TIME:        20:08[EST]|
| NRC NOTIFIED BY:  REINSBURROW                  |LAST UPDATE DATE:  01/11/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MIKE ERNSTES         R2      |
|10 CFR SECTION:                                 |                             |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP           |                             |
|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  |100      Power Operation  |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| FAILURE OF A REACTOR CORE ISOLATION COOLING (RCIC) BYPASS TO CONDENSATE      |
| STORAGE TANK VALVE TO FULLY STROKE DURING STROKE TIME TESTING                |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "EVENT:  At 2008 on 12/20/00 during performance of OPT-10.1.8 (RCIC System   |
| Valve Operability Test), the 2-E51-F022 (RCIC bypass to condensate storage   |
| tank) failed to fully stroke during stroke timing of the valve.  A valve     |
| thermal overload annunciator was received.  This rendered the Brunswick Unit |
| 2 RCIC system inoperable.  RCIC was not in operation at the time of this     |
| failure."                                                                    |
|                                                                              |
| "INITIAL SAFETY SIGNIFICANCE EVALUATION:  Minimal safety significance.       |
| Remaining ECCS systems are operable."                                        |
|                                                                              |
| "CORRECTIVE ACTION(S):  Determine the cause of the 2-E51-F022 valve failure. |
| Return the Unit 2 RCIC system to operable following repair of 2-E51-F022."   |
|                                                                              |
| The licensee stated that this event did not result in any radiological       |
| release or reactor coolant leaks.  The licensee also stated that all systems |
| functioned as required and that there was nothing unusual or misunderstood.  |
| This event placed the unit in a 14-day technical specification limiting      |
| condition for operation.                                                     |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
|                                                                              |
| * * * RETRACTION ON 01/11/01 AT 1059ET BY CHARLES ELBERFELD TAKEN BY         |
| MACKINNON* * *                                                               |
|                                                                              |
| Upon further evaluation, it has been determined that the conditions          |
| resulting in the RCIC system being declared inoperable for Technical         |
| Specification LCO 3.5.3 did not result in a loss of the system's function to |
| remove residual heat.  The function of the RCIC system is to respond to      |
| transient events by providing makeup coolant to the reactor.  The RCIC       |
| system is not an Engineered Safety Feature system, and no credit is taken in |
| the Updated Final Safety Analysis Report (UFSAR) for RCIC system operation   |
| mitigating the consequences of a postulated accident.  The RCIC system is    |
| designed to operate either automatically or manually following reactor       |
| pressure vessel (RPV) isolation accompanied by a loss of normal coolant flow |
| from the reactor feedwater system to provide adequate core cooling and       |
| control of the RPV water level.  Its operational purpose is to provide an    |
| alternate source of reactor coolant to the vessel and to provide sufficient  |
| cooling to remove residual heat following reactor shutdown and loss of       |
| feedwater flow without requiring depressurization of the reactor. Neither    |
| the 2-E51-F022 being de-energized in the open position, nor the questionable |
| capability of the 2-E51-F029 resulted in the loss  of the ability of the     |
| RCIC system to remove residual heat.                                         |
|                                                                              |
| In the case of the RCIC Bypass to Condensate Storage Tank valve 2-E51-F022,  |
| with the valve de-energized in the open position, injection flow into the    |
| RPV is not diverted to the Condensate Storage Tank, or into the High         |
| Pressure Coolant Injection system due to additional closed valves in the     |
| test flow path. Therefore, if the RCIC system had been called upon to        |
| perform its needed function to remove residual heat, the system would have   |
| performed as required.                                                       |
|                                                                              |
| In the case of the RCIC Torus Suction valve 2-E51-F029, although the ability |
| for the RCIC system sump suction to align to the Torus must be available to  |
| meet its Technical Specification LCO Operability requirements, the RCIC      |
| system has the capacity to meet its function to remove residual heat when    |
| aligned to the Condensate Storage Tank. Although the RCIC system is a single |
| train injection system, it has redundant suction flow paths that are fully   |
| capable of meeting these injection requirements.  Loss of one suction flow   |
| path does not prevent the RCIC system from performing its required function  |
| to remove residual heat.                                                     |
|                                                                              |
| Subsequently, it has been determined that the malfunction of the RCIC system |
| components did not adversely impact that system function to remove residual  |
| heat.  Carolina Power and Light Company has determined that this event does  |
| not meet 10 CFR 50.72 or 10 CFR 50.73 reporting criteria and this            |
| notification is being retracted.                                             |
| NRC R2DO (Chuck Ogle) notified.                                              |
|                                                                              |
| The NRC Resident Inspector was notified of this retraction by the licensee.  |
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|Power Reactor                                    |Event Number:   37659       |
+------------------------------------------------------------------------------+
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| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 01/11/2001|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 17:37[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        01/11/2001|
+------------------------------------------------+EVENT TIME:        17:15[EST]|
| NRC NOTIFIED BY:  ERIC OLSON                   |LAST UPDATE DATE:  01/11/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |DAVID LEW            R1      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| DISCOVERY OF CONDITION INVOLVING INABILITY OF THE LOW PRESSURE COOLANT       |
| INJECTION (LPCI) SYSTEM TO PERFORM DESIGN FUNCTION BETWEEN APRIL 1999 AND    |
| JANUARY 2001                                                                 |
|                                                                              |
| "On 1/2/01, discovered incorrect relays (27-B2X2 and 27-B2Z2) had been       |
| installed in Bus B6 (480 VAC swing bus) during RFO 12 (April, 1999).  The    |
| bus transfer logic was declared inoperable at the time and entry was made    |
| into a 7-day cold shutdown LCO for LPCI.                                     |
|                                                                              |
| "Further analysis of the circuit has determined that the B6 Bus would have   |
| remained de-energized following a loss of offsite power if the 'A' side      |
| power supply became unavailable (i.e., 'A' Emergency Diesel failed or 'A'    |
| 125 VDC Battery failed).                                                     |
|                                                                              |
| "This condition is outside the design in accordance with Pilgrim Station     |
| FSAR.                                                                        |
|                                                                              |
| "The relays were replaced with the correct design and the LPCI LCO cleared   |
| at approximately 0745 Sunday, January 7, 2001."                              |
|                                                                              |
| The licensee will inform the NRC resident inspector.                         |
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