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Event Notification Report for January 25, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           01/24/2001 - 01/25/2001

                              ** EVENT NUMBERS **

37682  37683  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37682       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 01/24/2001|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 07:36[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/23/2001|
+------------------------------------------------+EVENT TIME:        07:25[EST]|
| NRC NOTIFIED BY:  ABRAMSKI                     |LAST UPDATE DATE:  01/24/2001|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:                                |STEVEN DENNIS        R1      |
|10 CFR SECTION:                                 |                             |
|*INB 50.72(b)(3)(v)(B)   POT RHR INOP           |                             |
|*IND 50.72(b)(3)(v)(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                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION SYSTEM DECLARED INOPERABLE.                  |
|                                                                              |
| The flow controller for the High Pressure Coolant Injection (HPCI) system is |
| indicating approximately 1400 gpm with the HPCI system in the standby        |
| condition.  Because the cause of this condition is not known at this time,   |
| the HPCI system is considered inoperable.                                    |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37683       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 01/24/2001|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 12:20[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        01/24/2001|
+------------------------------------------------+EVENT TIME:        03:30[EST]|
| NRC NOTIFIED BY:  KEVIN DONNELLY               |LAST UPDATE DATE:  01/24/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |STEVEN DENNIS        R1      |
|10 CFR SECTION:                                 |                             |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       86       Power Operation  |86       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HR REPORT REQUIRED BY STATION ADMINISTRATIVE ORDERS FOR THE FIRE          |
| PROTECTION PLAN                                                              |
|                                                                              |
| "Indian Point #2 Station                                                     |
|                                                                              |
| "High Pressure Fire Header Impairment                                        |
|                                                                              |
| "Fire Impairment and Surveillance per Station Administration Order 703.      |
|                                                                              |
| "NRC event # 37683. The high pressure Fire Water Protection System is        |
| degraded due to planned maintenance work. The inner and outer high-pressure  |
| fire headers are split to provide protection for work on the valves for 12   |
| Fire Main Booster Pump. 12 Fire main booster pump is inoperable during this  |
| tag-out. The diesel fire pump is in service as the alternate fire protection |
| for the outside fire header. 11 and 12 fire maintenance pumps are supplying  |
| the inside header with 11 Fire Main Booster Pump available as a back up.     |
| SAO-703 states one fire main booster pump out of service is a 7-day action   |
| statement to return it to operable status. The headers being separated or    |
| any part of the fire protection piping or valves not being able to perform   |
| its function other than the specific instances described in SAO-703 requires |
| an alternate fire protection system shall be established. This was           |
| established within 24 hours to ensure compliance with SAO-703 as described   |
| above. A special report shall be submitted to the NRC Regional Administrator |
| of the Region 1 Office outlining this event within 14 Days."                 |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
+------------------------------------------------------------------------------+


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