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Event Notification Report for March 14, 2003








                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           03/13/2003 - 03/14/2003



                              ** EVENT NUMBERS **



39554  39655  39660  39664  39665  39667  39668  39669  



!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!

+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39554       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: FERMI                    REGION:  3  |NOTIFICATION DATE: 02/01/2003|

|    UNIT:  [2] [] []                 STATE:  MI |NOTIFICATION TIME: 09:41[EST]|

|   RXTYPE: [2] GE-4                             |EVENT DATE:        02/01/2003|

+------------------------------------------------+EVENT TIME:        01:45[EST]|

| NRC NOTIFIED BY:  JEFF GROFF                   |LAST UPDATE DATE:  03/13/2003|

|  HQ OPS OFFICER:  HOWIE CROUCH                 +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MARK RING            R3      |

|10 CFR SECTION:                                 |                             |

|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|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                                   

+------------------------------------------------------------------------------+

| LOSS OF A SAFETY FUNCTION DUE TO ALL FOUR EMERGENCY DIESEL GENERATORS BEING  |

| DECLARED INOPERABLE                                                          |

|                                                                              |

| The following information was received from the Licensee via facsimile:      |

|                                                                              |

| "At 0145 hours [EST] on 2/1/2003, all four Emergency Diesel Generators       |

| (EDGs) were declared inoperable following discovery of a Fuel Oil leakage    |

| drain path change that was installed to prevent Fuel Oil leakage from        |

| reaching the ground water.                                                   |

|                                                                              |

| "This change involved the installation of plastic sleeves on the fuel oil    |

| drains for all four EDGs to reroute the fuel oil drains to a catch basin.    |

| The normal drain path is through the RHR [Residual Heat Removal] Complex     |

| (which houses the EDGs) drain system to the chemical pond.  This change was  |

| installed after a crack was discovered in a 21 inch concrete line in the     |

| drain path from the RHR Complex Drain Sump to the Chemical Pond. This change |

| was installed on 01/17/03.                                                   |

|                                                                              |

| "While running EDG 11 for post maintenance testing following a scheduled     |

| maintenance outage, fuel oil in a drain sleeve backed up and spilled out of  |

| a vent on the fuel oil drain header.  This spillage resulted in a small      |

| lagging fire.  EDG 11 was immediately shutdown and the fire was extinguished |

| within a few minutes.  No significant damage to EDG 11 was caused by the     |

| fire.  Since all four EDGs had a similar fuel oil drain configuration, they  |

| were declared inoperable at 0145 hours and Technical Specification 3.8.1,    |

| Condition B was entered, which requires restoration of one division of the   |

| EDGs within 2 hours.                                                         |

|                                                                              |

| "At 0329 hours, the normal fuel oil drain configuration was restored for EDG |

| 13 and EDG 14 (Division 2) and Technical Specification 3.8.1, Condition B    |

| was exited.  At 0345 hours, the normal fuel oil drain configuration was      |

| restored for EDG 12 (Division 1). EDG 11 remains inoperable until the        |

| completion of post maintenance testing.                                      |

|                                                                              |

| "This notification is being made in accordance with 10CFR50.72(b)(3)(v)[(D)] |

| due to all four EDGs being inoperable causing the loss of a safety           |

| function."                                                                   |

|                                                                              |

| The fire was extinguished without offsite assistance and there were no       |

| injuries due to the fire.                                                    |

|                                                                              |

| The Licensee has notified the NRC Resident Inspector.                        |

|                                                                              |

| *** RETRACTION AT 1118 EST ON 3/13/03 FROM PATRICK FALLON TO ERIC THOMAS     |

| ***                                                                          |

|                                                                              |

| "While running EDG (Emergency Diesel Generator) 11 for post maintenance      |

| testing following a scheduled maintenance outage on February 1, 2003, fuel   |

| oil in a drain sleeve backed up and spilled out of a vent on the fuel oil    |

| drain header. This spillage resulted in a small fire. The fire caused no     |

| damage to EDG 11. Since all four EDGs had a similar temporary fuel oil drain |

| configuration, they were declared inoperable. The normal fuel oil drain      |

| configuration was restored within the Completion Time of Technical           |

| Specification 3.8.1, Condition B.  Notification was made in accordance with  |

| 10 CFR 50.72(b)(3)(v) due to all four EDGs being declared inoperable causing |

| the loss of a safety function.                                               |

|                                                                              |

| "The cause of the fire is believed to be excessive fuel oil leaking from the |

| EDG 11 fuel injector compartment onto the exhaust manifold. (The cause was   |

| initially reported as normal fuel injector leakage backing up into the fuel  |

| oil drain header due to the temporary drain configuration). The injectors    |

| allowed an abnormally high rate of fuel oil leakage into the fuel oil drain  |

| header for EDG 11 only. The fuel oil drain rates for EDGs 12, 13, and 14     |

| were observed to be normal during subsequent surveillance testing, and       |

| within the capability of the temporary fuel oil drain configuration.         |

|                                                                              |

| "Therefore, EDGs 12, 13, and 14 were capable of performing their safety      |

| function and there was no common mode failure, as a result of the temporary  |

| drain configuration. This condition is therefore not reportable under 10 CFR |

| 50.72(b)(3)(v). The original notification, Event Number 39554, is            |

| retracted."                                                                  |

|                                                                              |

| The Licensee has notified the NRC Resident Inspector.                        |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|General Information or Other                     |Event Number:   39655       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| REP ORG:  TEXAS DEPARTMENT OF HEALTH           |NOTIFICATION DATE: 03/10/2003|

|LICENSEE:  PROFESSIONAL SERVICES INDUSTRIES, PSI|NOTIFICATION TIME: 14:54[EST]|

|    CITY:  HOUSTON                  REGION:  4  |EVENT DATE:        03/08/2003|

|  COUNTY:                            STATE:  TX |EVENT TIME:        12:45[CST]|

|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  03/10/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |MARK SHAFFER         R4      |

|                                                |KEVIN HSUEH          NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  GLENN CORBIN                 |                             |

|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+------------------------------------------------------------------------------+



                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| AGREEMENT STATE REPORT: STOLEN TROXLER MOISTURE DENSITY GAUGE                |

|                                                                              |

|                                                                              |

| "A Troxler model #3430 (serial number 27095), portable moisture/density      |

| gauge was reported stolen from the Texas Medical Center construction project |

| site located at 2450 Holcomb, Houston, Texas between 12:45 p.m.  and 1:30    |

| p.m. CT on Saturday, March 8, 2003.  This device is bright yellow,           |

| approximately 11" long x 8" wide x 5" tall with two metal posts              |

| approximately 18" tall protruding from the top of the device and a locked    |

| handle at the top. The device contains two sealed sources (isotopes)         |

| double-encapsulated in stainless steel, and is licensed by the Texas         |

| Department of Health.  When not in use, the device emits low-level energy    |

| equivalent to a single chest x-ray, which poses no threat unless the device  |

| is tampered with.                                                            |

|                                                                              |

| "A police report has been filed with the Houston Police Department.          |

|                                                                              |

| "The company is offering a $500.00 reward for the return of the device on    |

| the 'no-questions-asked' bases.  If found, please do not move the device and |

| contact the Houston Police Department  and refer to police report no.        |

| 032141303E.  If anyone has any information regarding the theft of the device |

| please [call PSI]."                                                          |

|                                                                              |

| The State of Texas believes the Troxler moisture density gauge contains 10   |

| millicuries of Cesium-137 and 40 millicuries of Am/Be-241.                   |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|General Information or Other                     |Event Number:   39660       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| REP ORG:  OR DEPT OF HEALTH RAD PROTECTION     |NOTIFICATION DATE: 03/11/2003|

|LICENSEE:  ROGUE VALLEY MEDICAL CENTER          |NOTIFICATION TIME: 11:59[EST]|

|    CITY:  MEDFORD                  REGION:  4  |EVENT DATE:        03/11/2003|

|  COUNTY:  JACKSON                   STATE:  OR |EVENT TIME:             [PST]|

|LICENSE#:  ORE-90064             AGREEMENT:  Y  |LAST UPDATE DATE:  03/11/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |MARK SHAFFER         R4      |

|                                                |KEVIN HSUEH          NMSS    |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  EDWIN WRIGHT                 |                             |

|  HQ OPS OFFICER:  JOHN MacKINNON               |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|NAGR                     AGREEMENT STATE        |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+------------------------------------------------------------------------------+



                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| AGREEMENT STATE REPORT: MISSING BRACHEYTHERAPY IRIDIUM-192 SEED.             |

|                                                                              |

| Dr. Sinnott called to report the loss of an Ir-192 bracheytherapy seed with  |

| a current activity of 6 millicuries.  The source was last visually           |

| inventoried in December 2002.  The loss was noted yesterday, March 9, 2002,  |

| while the physicist was packaging sources for return to the manufacturer.    |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39664       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 03/13/2003|

|    UNIT:  [] [2] []                 STATE:  AZ |NOTIFICATION TIME: 11:14[EST]|

|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        02/27/2003|

+------------------------------------------------+EVENT TIME:        09:28[MST]|

| NRC NOTIFIED BY:  DUANE KANITZ                 |LAST UPDATE DATE:  03/13/2003|

|  HQ OPS OFFICER:  YAMIR DIAZ                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MARK SHAFFER         R4      |

|10 CFR SECTION:                                 |                             |

|AINV 50.73(a)(1)         INVALID SPECIF SYSTEM A|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|2     N          Y       98       Power Operation  |98       Power Operation  |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| INVALID SPECIFIED SYSTEM ACTUATION 60 DAY REPORT                             |

|                                                                              |

| "The following event description is based on information currently           |

| available. If 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.          |

|                                                                              |

| "On February 17, 2003, at approximately 0928 Mountain Standard Time, Palo    |

| Verde Nuclear Generating Station Unit 2 experienced an invalid actuation     |

| (start) of the 'A' Emergency Diesel Generator (EDG). EDG 'A'  inadvertently  |

| started when an Instrument and Control technician, performing the ESFAS      |

| train 'A' subgroup relay functional and response time surveillance test,     |

| completed a step in the test procedure out of sequence. The technician       |

| verified the status of [actuated] an ESFAS relay contact, which generates an |

| EDG start signal, before the 'A' EDG control mode switch was placed in the   |

| OFF  position.                                                               |

|                                                                              |

| "This report is not considered an LER.                                       |

|                                                                              |

| "EDG 'A' was the specific System and train that actuated.                    |

|                                                                              |

| "EDG 'A' started in the Emergency Mode. The train actuation was complete.    |

|                                                                              |

| "EDG 'A' started and came up to rated speed and voltage as designed.         |

|                                                                              |

| "This report is being made under 10 CFR 50.73 (a) (2) (iv) (A)."             |

|                                                                              |

| The licensee has notified the NRC Resident Inspector.                        |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39665       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 03/13/2003|

|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 13:38[EST]|

|   RXTYPE: [1] GE-2                             |EVENT DATE:        03/13/2003|

+------------------------------------------------+EVENT TIME:        06:15[EST]|

| NRC NOTIFIED BY:  CIGANIK                      |LAST UPDATE DATE:  03/13/2003|

|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MOHAMED SHANBAKY     R1      |

|10 CFR SECTION:                                 |                             |

|ACOM 50.72(b)(3)(xiii)   LOSS COMM/ASMT/RESPONSE|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|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                                   

+------------------------------------------------------------------------------+

| MAJOR LOSS OF EMERGENCY PREPAREDNESS CAPABILITIES                            |

|                                                                              |

| The licensee was notified by Ocean County that their alarm panel indicated   |

| the radio power to the prompt notification sirens had failed with unknown    |

| affect on the sirens operation.  The Licensee Technicians were dispatched    |

| and had to reboot a computer to clear the alarm.  Sirens would not operate   |

| until the computer was rebooted.  Sirens tested satisfactory @ 0930 hours.   |

|                                                                              |

| This notification was made because it can not be determined if the Ocean     |

| County siren activation technicians possess the knowledge and skills to      |

| reboot this computer if siren activation would have been required.  If it is |

| later determined  that the technicians did possess the required knowledge    |

| and skills, this notification may be retracted.                              |

|                                                                              |

| The NRC Resident Inspector was notified along with local agencies.           |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39667       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 03/13/2003|

|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 16:32[EST]|

|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        03/13/2003|

+------------------------------------------------+EVENT TIME:        08:00[CST]|

| NRC NOTIFIED BY:  BREDEMAN                     |LAST UPDATE DATE:  03/13/2003|

|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |MARK SHAFFER         R4      |

|10 CFR SECTION:                                 |                             |

|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|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                                   

+------------------------------------------------------------------------------+

| ERROR IN THE CURRENT SAFETY ANALYSIS FOR A STEAM GENERATOR TUBE RUPTURE      |

|                                                                              |

| "On March 13, 2003 while operating at 100% power, Callaway Plant determined  |

| a problem existed in the current safety analysis for a steam generator tube  |

| rupture accident accompanied by an overfill condition of the ruptured steam  |

| generator. This problem was discovered while reviewing a future plant        |

| modification package.   The current FSAR analysis concluded that an overfill |

| condition would not occur during a tube rupture accident.                    |

|                                                                              |

| "Through investigations instigated during the modification review process,   |

| it was determined that for current plant conditions, an overfill condition   |

| could result if an auxiliary feedwater control valve supplying the ruptured  |

| steam generator were to fail open.   In this case, it was concluded that the |

| ruptured steam generator would overfill and water would be released through  |

| the steam generator safety valves, resulting in a radioactive release to the |

| environment greater than allowed by regulatory guidance.   Since this        |

| accident was not adequately incorporated in the FSAR, specific procedural    |

| time limits for operator actions had not been developed.   This lack of      |

| credited operator time limits coupled with past plant modifications result   |

| in a potential to exist for the ruptured steam generator overfill scenario.  |

|                                                                              |

| "Current Technical Specifications allow a reactor coolant system Dose        |

| Equivalent Iodine (DEI) value of 1.0 microcurie per gram.  To assure         |

| compliance with existing regulatory guidance, plant procedures have been     |

| changed to administratively reduce the steady state DEI limit to 0.3         |

| microcurie per gram, a value that has not been exceeded in the last three    |

| years. Current steady state DEI concentration in the reactor coolant system  |

| is 0.001769 microcurie per gram.  The new lower DEI limit will ensure that   |

| if an overfill condition were to occur during a steam generator tube         |

| rupture, post accident radiological consequences would not exceed the limits |

| imposed by the FSAR and the Standard Review Plan."                           |

|                                                                              |

| The NRC Resident Inspector was notified.                                     |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Hospital                                         |Event Number:   39668       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| REP ORG:  REGIONS HOSPITAL                     |NOTIFICATION DATE: 03/13/2003|

|LICENSEE:  REGIONS HOSPITAL                     |NOTIFICATION TIME: 17:27[EST]|

|    CITY:  ST PAUL                  REGION:  3  |EVENT DATE:        03/07/2003|

|  COUNTY:                            STATE:  MN |EVENT TIME:        09:00[CST]|

|LICENSE#:  22-02003-04           AGREEMENT:  N  |LAST UPDATE DATE:  03/13/2003|

|  DOCKET:                                       |+----------------------------+

|                                                |PERSON          ORGANIZATION |

|                                                |KENNETH O'BRIEN      R3      |

|                                                |                             |

+------------------------------------------------+                             |

| NRC NOTIFIED BY:  SOGARD                       |                             |

|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |

+------------------------------------------------+                             |

|EMERGENCY CLASS:          NON EMERGENCY         |                             |

|10 CFR SECTION:                                 |                             |

|BSUR 20.1906(d)(1)       SURFACE CONTAM LEVELS >|                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+------------------------------------------------------------------------------+



                                   EVENT TEXT                                   

+------------------------------------------------------------------------------+

| SURFACE CONTAMINATION ON AMMO BOX GREATER THAN ACCEPTABLE LIMITS             |

|                                                                              |

| On March 7 @ 0900 an ammo box was received from Syncor that measured         |

| 0.3mr/hr at the surface and had a wipe of approximately 9707 DPM (2200 DPM   |

| is acceptable).   Syncor was notified of the contamination on the box.  The  |

| box was put into the hospital's storage area until March 11 when the         |

| measurements taken were at background.  The box was than returned to Syncor. |

+------------------------------------------------------------------------------+



+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39669       |

+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+

| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 03/13/2003|

|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 18:35[EST]|

|   RXTYPE: [1] GE-3                             |EVENT DATE:        03/13/2003|

+------------------------------------------------+EVENT TIME:        14:30[CST]|

| NRC NOTIFIED BY:  JACK EARCLEY                 |LAST UPDATE DATE:  03/13/2003|

|  HQ OPS OFFICER:  RICH LAURA                   +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |KENNETH O'BRIEN      R3      |

|10 CFR SECTION:                                 |                             |

|AUNA 50.72(b)(3)(ii)(B)  UNANALYZED CONDITION   |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|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                                   

+------------------------------------------------------------------------------+

| DEGRADED APPENDIX "R" BARRIER AT MONTICELLO                                  |

|                                                                              |

| "During inspection of penetration FZ-4900 in the upper 4KV room it was       |

| discovered there was a portion of the penetration seal that was degraded     |

| which caused the upper and lower 4KV rooms to communicate with each other.   |

| Penetration seal FZ-4900 is a gypsum wall board assembly approximately 18    |

| inches wide 4 foot high and 24 foot long. The degraded part of the           |

| penetration is approximately 1 inch by 4 inch hole. The upper and lower 4 KV |

| areas are required to be separated in accordance with 10CFR50 Appendix R     |

| requirements."                                                               |

|                                                                              |

| The licensee indicated they established a fire watch as a compensatory       |

| measure.                                                                     |

|                                                                              |

| The NRC Resident Inspector was notified.                                     |

+------------------------------------------------------------------------------+