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Event Notification Report for March 12, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/09/2001 - 03/12/2001

                              ** EVENT NUMBERS **

37816  37817  37818  37819  37820  37821  37822  37823  37824  37825  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37816       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 03/09/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 04:30[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        03/09/2001|
+------------------------------------------------+EVENT TIME:        01:30[CST]|
| NRC NOTIFIED BY:  TIM ROGERS                   |LAST UPDATE DATE:  03/09/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|*SHU 50.72(b)(2)(i)      PLANT S/D REQD BY TS   |                             |
|*ESF 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     A          N       0        Refueling        |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MODE CHANGE DUE TO LITERAL INTERPRETATION OF REQUIREMENTS                    |
|                                                                              |
| "To meet compliance with literal interpretation of Tech Spec 3.7.A.5 and     |
| 3.8.B.6, containment venting and purging using SBGT is required above 'Cold  |
| Shutdown.'  Plant is < 212, all rods in BUT mode switch was in 'Refuel.' To |
| comply with Tech Specs, a Tech Spec shutdown with mode switch was performed. |
| All rods were already in but it wasn't a preplanned shutdown evolution.      |
| Other similar 'Cold Shutdown' Tech Spec compliance issues are being looked   |
| at."                                                                         |
|                                                                              |
| An automatic scram signal was generated when the mode switch was taken to    |
| the 'Shutdown' position. Although all control rods were already inserted,    |
| the licensee considers this action to be reportable as a valid safety system |
| actuation. The NRC resident inspector will be informed of this event by the  |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37817       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 03/09/2001|
|    UNIT:  [2] [] []                 STATE:  NY |NOTIFICATION TIME: 07:18[EST]|
|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        03/09/2001|
+------------------------------------------------+EVENT TIME:        01:45[EST]|
| NRC NOTIFIED BY:  FRANK KICH                   |LAST UPDATE DATE:  03/09/2001|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD BELLAMY       R1      |
|10 CFR SECTION:                                 |ED GOODWIN           NRR     |
|NONR                     OTHER UNSPEC REQMNT    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24 Hour Notification of High Pressure Fire Water Fire Protection System      |
| Impairment per Station Administration Order (SAO) 124 Item 64 and SAO-703    |
| Addendum I Item 2.b.1.b.i.                                                   |
|                                                                              |
| "At 0145 on March 9, 2001, 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 to maintain header pressure for  |
| the outside fire header. 11 Fire Main Booster Pump is in operation providing |
| fire header pressure for the inside fire header. Contingency hoses have been |
| staged to provide fire water supply to cross connect the inside and outside  |
| headers in the event of a failure on either header. SAO-703 Addendum I Item  |
| 2.a.1.a 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. The alternate fire |
| protection system was established within 24 hours to ensure compliance with  |
| SAO-703 as described above. A special report will 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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37818       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALISADES                REGION:  3  |NOTIFICATION DATE: 03/09/2001|
|    UNIT:  [1] [] []                 STATE:  MI |NOTIFICATION TIME: 09:31[EST]|
|   RXTYPE: [1] CE                               |EVENT DATE:        02/08/2001|
+------------------------------------------------+EVENT TIME:        14:37[EST]|
| NRC NOTIFIED BY:  R. VINCENT                   |LAST UPDATE DATE:  03/09/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| MISSING LOW ACTIVITY SOURCE                                                  |
|                                                                              |
| "During a routine inventory of licensed radioactive sources, one low         |
| activity, mixed isotope source could not be accounted for. The source        |
| contained a total of approximately 0.992 microcurie, of which approximately  |
| 0.154 microcurie was americium-241. Since the quantity of americium-241 in   |
| this source was more than ten times greater than the quantity specified in   |
| Appendix C of 10CFR20, a telephone report is required in accordance with     |
| 10CFR20.2201(a)(1)(ii). None of the other isotopes in the source exceeded    |
| reportable quantities specified in Appendix C. The low activity and          |
| relatively large physical size of the source are such that it would not be a |
| significant radiological hazard. A search of the site failed to locate the   |
| source. It is not likely that a person could have inadvertently carried the  |
| source out of the radiologically controlled area (RCA) on his body since the |
| source would have caused the RCA exit monitors to alarm. We have concluded   |
| that the source was most likely discarded by mistake inside the RCA into a   |
| yellow trash bag with other radioactive waste. The low level radioactive     |
| waste from the time period in question was shipped off site to a licensed    |
| vendor and has been incinerated."                                            |
|                                                                              |
| The NRC resident inspector has been informed of this event by the licensee.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37819       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  AGILENT TECHNOLOGIES                 |NOTIFICATION DATE: 03/09/2001|
|LICENSEE:  AGILENT TECHNOLOGIES                 |NOTIFICATION TIME: 15:18[EST]|
|    CITY:  WILMINGTON               REGION:  1  |EVENT DATE:        02/16/2001|
|  COUNTY:                            STATE:  DE |EVENT TIME:        12:00[EST]|
|LICENSE#:  07-28762-01           AGREEMENT:  N  |LAST UPDATE DATE:  03/09/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |RONALD BELLAMY       R1      |
|                                                |JOSIE PICCONE        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  DAVID BENNET                 |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB2 20.2201(a)(1)(ii)   LOST/STOLEN LNM>10X    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| Agilent Technologies reported the loss of two electron capture detectors.    |
| Each detector contains a 15 mCi Ni-63 source.  Because the Ni-63 is plated   |
| on the inside of the device and Ni-63 is a low energy Beta emitter, the risk |
| of exposure to the public is low.  The detectors were last accounted for in  |
| December 1995.                                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   37820       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  ILLINOIS DEPT OF NUCLEAR SAFETY      |NOTIFICATION DATE: 03/09/2001|
|LICENSEE:  LOYOLA UNIVERSITY MEDICAL CENTER     |NOTIFICATION TIME: 15:57[EST]|
|    CITY:  MAYWOOD                  REGION:  3  |EVENT DATE:        03/08/2001|
|  COUNTY:                            STATE:  IL |EVENT TIME:        12:00[CST]|
|LICENSE#:  IL-01131-02           AGREEMENT:  Y  |LAST UPDATE DATE:  03/09/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN MADERA          R3      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JOE KLINGER                  |                             |
|  HQ OPS OFFICER:  DOUG WEAVER                  |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MEDICAL MISADMINISTRATION                                                    |
|                                                                              |
| The following text was taken from an email sent to the NRC's Operations      |
| Center from the State of Illinois.                                           |
|                                                                              |
| The RSO at Loyola University Medical Center, IL-01131-02, Maywood, IL,       |
| called at approximately 12:30 p.m., 3/9/01, to report a reportable event     |
| involving the Cordis Intravascular Brachytherapy (IVB)                       |
| system.   He stated that two patients undergoing cardiac therapy on the      |
| previous day, had been treated with the Ir-192 seeds to prevent restenosis   |
| in a stent.  The prescribed dose was 8 gray (800 rads) to the tunica media   |
| layer of the heart.  However, the calculated dose to one of the patients     |
| was12.5 gray (1250 rads) (56% overdose) and 14.3 gray (1,430 rads) (79%      |
| overdose).                                                                   |
|                                                                              |
| The cause of the problem appears to be due to a new method for this          |
| institution to determine the actual dose to the intended organ.  In the      |
| past, dwell times were based on 14 gray being delivered at 2 mm distance     |
| from the radioactive sources. This new procedure requires an intravascular   |
| ultrasound device to be used and measurements from the intended treatment    |
| portion of the heart and the sources are determined.  These measurements     |
| then determine the dwell time for the prescribed dose.  This new measurement |
| method and possible communication problems while taking the measurements and |
| using the measurements contributed to the problem.  No further use of this   |
| system will be conducted until these problems are resolved and the Radiation |
| Safety Committee and the Department are satisfied that there will be no      |
| recurrence.                                                                  |
|                                                                              |
| .                                                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37821       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 03/09/2001|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 20:46[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        03/09/2001|
+------------------------------------------------+EVENT TIME:        12:51[CST]|
| NRC NOTIFIED BY:  GARY OLMSTEAD                |LAST UPDATE DATE:  03/09/2001|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |WILLIAM JOHNSON      R4      |
|10 CFR SECTION:                                 |                             |
|*ESF 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     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| LOSS OF BOTH CONTROL ROD DRIVE MOTOR GENERATORS CAUSES REACTOR TRIP          |
|                                                                              |
| During performance of work on the 'B' Rod Drive Motor Generator set, the     |
| output breaker for 'A' Rod Drive Motor Generator set opened causing a loss   |
| of power to the Rod Control System.  The cause of the 'A' Rod Drive Motor    |
| Generator set output breaker opening is being investigated.  With a loss of  |
| power, all rods were de-energized and inserted into the core.  Rod K-10      |
| developed an alarm and the problem was determined to be a faulty circuit     |
| card.  The circuit card was replaced and the problem corrected.              |
|                                                                              |
| This event resulted in a Reactor Protection System (RPS) actuation, when     |
| rods were inserted, an Over Temperature delta T (OTdeltaT) trip was          |
| generated which generated the RPS actuation.  After the RPS system actuated, |
| an Auxiliary Feedwater System actuation was generated.                       |
|                                                                              |
| It was concluded this event is reportable per 10CFR50.72(b)(3)(iv)(A)        |
| since:                                                                       |
| (1) The actuation of the Reactor Protection System occurred after the rods   |
| were at the bottom of the Reactor core (i.e. shut down) as indicated by      |
| computer point alarm printout.                                               |
|                                                                              |
| The NRC Resident inspector was notified of this event by the licensee        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37822       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SUSQUEHANNA              REGION:  1  |NOTIFICATION DATE: 03/10/2001|
|    UNIT:  [] [2] []                 STATE:  PA |NOTIFICATION TIME: 04:50[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/10/2001|
+------------------------------------------------+EVENT TIME:        04:14[EST]|
| NRC NOTIFIED BY:  ARDLE KISSINGER              |LAST UPDATE DATE:  03/10/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RONALD BELLAMY       R1      |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       21       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| COURTESY NOTIFICATION FOR ENTRY INTO 10TH REFUELING                          |
|                                                                              |
| "This is a Courtesy Notification and does not fall within 10CFR50.72         |
| Guidelines.                                                                  |
|                                                                              |
| "Susquehanna Unit 2 was manually shutdown on 3/10/01 to enter its 10th       |
| Refueling and Inspection outage. At 1630 hours on 3/9/01, a controlled       |
| shutdown was commenced by reducing recirc flow and then inserting control    |
| rods. At 03:45 on 3/10/99, the Main Turbine was manually tripped with power  |
| at 17.5%. At 04:14 with power at 21% the reactor mode switch was taken to    |
| shutdown placing the unit in condition 3. All control rods fully inserted.   |
| Rx Water level dropped to approximately -1 inch as recorded on wide range    |
| instrumentation, and was restored using Feedwater. There were no ECCS        |
| initiations or Diesel Generator starts. No safety/relief valves lifted.      |
| There were no challenges to containment or fuel as a result of the           |
| shutdown.                                                                    |
|                                                                              |
| "The shutdown is continuing according to schedule and is scheduled to return |
| to service in 35 days."                                                      |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37823       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 03/10/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 18:59[EST]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        03/10/2001|
+------------------------------------------------+EVENT TIME:        17:05[CST]|
| NRC NOTIFIED BY:  P DECKER                     |LAST UPDATE DATE:  03/10/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN MADERA          R3      |
|10 CFR SECTION:                                 |                             |
|*UNA 50.72(b)(3)(ii)(B)  UNANALYZED COND OP     |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| DIFFERENTIAL PRESSURE TO OPEN THE SUPPRESSION CHAMBER TO DRYWELL VACUUM      |
| BREAKERS DISCREPANCIES WERE IDENTIFIED.                                      |
|                                                                              |
| During review of Inservice Testing requirements, while the plant was in      |
| shutdown, discrepancies were identified with acceptance criteria for the     |
| torque values used to determine the equivalent differential pressure to open |
| the suppression chamber to drywell vacuum breakers.  The measured torque     |
| values indicate that the differential pressure required to fully open the    |
| suppression chamber to drywell vacuum breakers would be greater than that    |
| assumed in containment analyses.  The suppression chamber to drywell vacuum  |
| breakers insure that the 2 psig external design pressure for the primary     |
| containment drywell suppression chamber and vent system is not exceeded and  |
| containment integrity is assured.                                            |
|                                                                              |
| The NRC Resident Inspector will be notified of this event by the licensee.   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37824       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 03/10/2001|
|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 22:29[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        03/10/2001|
+------------------------------------------------+EVENT TIME:        15:15[EST]|
| NRC NOTIFIED BY:  JAMES JOHNSTONE              |LAST UPDATE DATE:  03/10/2001|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|*SHU 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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       72       Power Operation  |71       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION (TS) SHUTDOWN                                        |
|                                                                              |
| "At time 2058 (EST) on 03/10/01, Unit 2 commenced a normal rampdown to cold  |
| shutdown for refueling.  The unit was in action statement that expires at    |
| 1515 on 03/11/01.  The action statement of TS 3.6.1.3.b had been entered at  |
| 1515 on 03/10/01 when 2-PT-62.1 failed.  This test was a routine pre-outage  |
| test on the containment equipment hatch personnel access air lock.  The unit |
| shutdown was planned for this date and time.  Repairs to the failed          |
| component will be made with unit in mode 5."                                 |
|                                                                              |
| The licensee thinks that the equipment hatch inner air lock door equalizing  |
| valve is leaking by.                                                         |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37825       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NORTH ANNA               REGION:  2  |NOTIFICATION DATE: 03/11/2001|
|    UNIT:  [] [2] []                 STATE:  VA |NOTIFICATION TIME: 04:28[EST]|
|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        03/11/2001|
+------------------------------------------------+EVENT TIME:        01:19[EST]|
| NRC NOTIFIED BY:  JAMES JOHNSTONE              |LAST UPDATE DATE:  03/11/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS DECKER        R2      |
|10 CFR SECTION:                                 |                             |
|*ESF 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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        N       0        Hot Standby      |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| TECHNICAL SPECIFICATION REQUIRED MANUAL REACTOR TRIP DURING PLANT SHUTDOWN   |
|                                                                              |
| At 0109 EST on 3/11/01 with the reactor already subcritical during the       |
| insertion of control bank 'B', the licensee noted that the group 2 step      |
| counter stopped moving at 53 steps.  Technical specification 3.1.3.3         |
| requires the reactor trip breakers to be opened within 15 minutes and at     |
| 0119 EST the licensee performed a manual reactor trip opening the trip       |
| breakers.  The plant is entering a refueling outage and the problem will be  |
| corrected before startup.                                                    |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
+------------------------------------------------------------------------------+