United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated With Events > Event Notification Reports > 2000

Event Notification Report for July 31, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           07/28/2000 - 07/31/2000

                              ** EVENT NUMBERS **

35406  37193  37194  37195  37196  37197  37198  37199  

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35406       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  PYCO, INC.                           |NOTIFICATION DATE: 02/25/1999|
|LICENSEE:  PYCO, INC.                           |NOTIFICATION TIME: 17:03[EST]|
|    CITY:  PENNDEL                  REGION:  1  |EVENT DATE:        02/25/1999|
|  COUNTY:                            STATE:  PA |EVENT TIME:        17:03[EST]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  07/28/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ROBERT HAAG          R2      |
|                                                |VERN HODGE (via fax) NRR     |
+------------------------------------------------+RICHARD BARKLEY      R1      |
| NRC NOTIFIED BY:  WILLIAM SZARY                |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 10 CFR PART 21 REPORT REGARDING FAULTY RESISTANCE TEMPERATURE DETECTORS      |
| (RTD)                                                                        |
|                                                                              |
| The following text is a portion of a facsimile received from PYCO, Inc.:     |
|                                                                              |
| "A deviation has been detected in that a limited number of 200 OHM DUPLEX    |
| RTD assemblies have been fabricated by PYCO using THIN-FILM RTD sensors      |
| instead of the WIRE-WOUND RTD sensors specified for the assembly. RTD        |
| assemblies fabricated using wire-wound sensors have been tested and          |
| qualified by PYCO for nuclear use under our nuclear qualification test       |
| program. RTD assemblies fabricated using thin-film sensors have not been     |
| tested by PYCO to IEEE-323 and IEEE-344 requirements."                       |
|                                                                              |
| "Externally, thin-film and wire-wound RTDs have the same physical            |
| appearance, shape, and electrical characteristics. Both the wire-wound and   |
| thin-film sensors meet the requirements of the International Industrial      |
| Standard IEC-751, 'Industrial Platinum Resistance Thermometer Sensors'."     |
|                                                                              |
| These RTDs have been sold to Carolina Power and Light and South Carolina     |
| Electric and Gas for use at the Robinson, Brunswick, and Summer plants.      |
|                                                                              |
| (Call the NRC Operations Center for a contact telephone number.)             |
|                                                                              |
| * * * UPDATE 1256EDT ON 7/28/00 TO S. SANDIN * * *                           |
|                                                                              |
| The following is a summary of the corrective actions completed:              |
|                                                                              |
| "PYCO has completed all corrective action activities for NCR Event# 35406.   |
| All affected Power Utilities have completed an 'Operability Evaluation and   |
| Determination of Acceptance' for potential thin-film RTD's in-service.       |
|                                                                              |
| "PYCO has completed an x--ray evaluation of all returned in-service or       |
| in-stock assemblies and identified those containing the incorrect thin-film  |
| sensor.                                                                      |
|                                                                              |
| "Assemblies found to have been manufactured with the correct wire-wound      |
| sensor were inspected, calibrated and returned to the utilities. Any         |
| assemblies found to contain the incorrect thin-film sensor were scrapped,    |
| and replacement assemblies containing the correct sensor were manufactured   |
| and shipped to the utilities.                                                |
|                                                                              |
| "As required by 10CFR Part 21, the following information is to provide       |
| notification of CORRECTIVE ACTION COMPLETION in connection with certain 200  |
| OHM duplex Resistance Temperature Detectors (RTD's) supplied to Carolina     |
| Power & Light - Robinson Plant and Brunswick Plant and South Carolina        |
| Electric & Gas - V.C. Summer Station."                                       |
|                                                                              |
| Notified R1DO(Shanbaky), R2DO(Cahill) and NRR(Hodge via fax).                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37193       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  IDAHO NAT ENGR & ENVIRONMENTAL LAB   |NOTIFICATION DATE: 07/27/2000|
|LICENSEE:  IDAHO NAT ENGR & ENVIRONMENTAL LAB   |NOTIFICATION TIME: 19:22[EDT]|
|    CITY:  IDAHO FALLS              REGION:  4  |EVENT DATE:        07/27/2000|
|  COUNTY:                            STATE:  ID |EVENT TIME:        15:55[MDT]|
|LICENSE#:                        AGREEMENT:  N  |LAST UPDATE DATE:  07/29/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |BILL JONES           R4      |
|                                                |ELLIS MERSCHOFF      RA      |
+------------------------------------------------+ELMO COLLINS         NMSS    |
| NRC NOTIFIED BY:  JOE GARCIA                   |CHARLES MILLER       IRO     |
|  HQ OPS OFFICER:  STEVE SANDIN                 |STEINDURF            FEMA    |
+------------------------------------------------+DOE, USDA, HHS (fax)         |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| COURTESY NOTIFICATION OF A DOE EMERGENCY DECLARATION AT AN INDEPENDENT SPENT |
| FUEL STORAGE INSTALLATION (ISFSI) IN IDAHO                                   |
|                                                                              |
| At 1555MDT, DOE INEEL declared a Site Area Emergency due to wildland fires   |
| on DOE controlled property.  The ISFSI containing the TMI spent fuel is not  |
| threatened.  This notification is a courtesy call only and does not involve  |
| the NRC Radiological Emergency Plan.  No NRC assistance is requested.        |
|                                                                              |
| DOE INEEL has notified the State of Idaho, all surrounding counties and DOE  |
| Headquarters.                                                                |
|                                                                              |
| *** UPDATE AT 0304 EDT ON 07/28/00 FROM JOE GARCIA AND FOREST HOLMS TO LEIGH |
| TROCINE ***                                                                  |
|                                                                              |
| This event status update was provided as a courtesy notification.   The Site |
| Area Emergency remains in progress.  There is a site-wide emergency action   |
| level in effect because of a wildland fire.  The TMI-2 ISFSI is located at   |
| the Idaho National Engineering & Environmental Laboratory (INEEL), but the   |
| Site Area Emergency does not impact the TMI-2 ISFSI.  However, INEEL has     |
| been directed by the Department of Energy (DOE) to notify the NRC when       |
| emergency action levels of this nature are in place.  The Site Area          |
| Emergency will remain in effect until the fire is extinguished.              |
|                                                                              |
| The following text is a portion of a facsimile received from the INEEL:      |
|                                                                              |
| "Description of Incident:  Wildland fire on the INEEL.  Fire suppression     |
| efforts continue.  Emergency response centers [are] operational at RWMC,     |
| CFA, INTEC, TRA, EOC with reduced staffing.  INTEC and TRA [are] continuing  |
| to monitor facilities."                                                      |
|                                                                              |
| The NRC operations officer notified the R4DO (Jones), R4RA (Merschoff), NMSS |
| EO (Collins), IRO (Miller), and the Federal Emergency Management Agency      |
| (FEMA) (Storer).  DOE, U.S. Department of Agriculture (USDA), Department of  |
| Health and Human Services (HHS), Environmental Protection Agency (EPA), and  |
| Department of Transportation (DOT) (via the National Response Center) were   |
| also notified via facsimile.                                                 |
|                                                                              |
|                                                                              |
| * * * UPDATE 1709EDT 7/29/00 FROM GREG BYBEE TO S. SANDIN * * *              |
|                                                                              |
| The Site Area Emergency was terminated at 1500MST.                           |
|                                                                              |
| The NRC operations officer notified the R4DO (Jones), R4RA (Merschoff), NMSS |
| EO (Collins), IRO (Miller), and the Federal Emergency Management Agency      |
| (FEMA) (Eaches).  DOE, U.S. Department of Agriculture (USDA), Department of  |
| Health and Human Services (HHS), Environmental Protection Agency (EPA), and  |
| Department of Transportation (DOT) (via the National Response Center) were   |
| also notified via facsimile.                                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   37194       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NOVARTIS PHARMACEUTICAL CORP         |NOTIFICATION DATE: 07/28/2000|
|LICENSEE:  NOVARTIS PHARMACEUTICAL CORP         |NOTIFICATION TIME: 10:07[EDT]|
|    CITY:  SUMMIT                   REGION:  1  |EVENT DATE:        06/29/2000|
|  COUNTY:                            STATE:  NJ |EVENT TIME:        15:50[EDT]|
|LICENSE#:  2908978-02            AGREEMENT:  N  |LAST UPDATE DATE:  07/28/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MOHAMED SHANBAKY     R1      |
|                                                |JOSIE PICCONE        NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KING                         |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAE1 20.2202(b)(1)       PERS OVEREXPOSURE      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NOVARTIS PHARMACEUTICAL CORPORATION REPORTED AN OVEREXPOSURE OF ONE OF THEIR |
| EMPLOYEES.                                                                   |
|                                                                              |
| An employee was working with carbon-14 in a hood wearing gloves when a drop  |
| of the organic compound solution went onto the gloves.  He immediately       |
| removed the gloves and noticed discoloration to his skin due to the chemical |
| going through the gloves to a certain extent.  He then proceeded to          |
| decontaminate himself using normal decontaminating procedures.  Surveys were |
| made and further decontamination was conducted, and based on their           |
| preliminary calculations at this point, the dose at skin depth of .007 cm is |
| approx. 100 rads(includes the step wise decon).  They do not believe he      |
| exceeded the NRC dose limit until early July.  The solution was on the tip   |
| of the left index finger where the skin is much thicker(approx. .04 cm) than |
| the NRC depth of skin dose calculation of .007 cm.  The dose, if the         |
| material is deposited on the surface of the skin, to the live tissue at a    |
| skin depth of .04 cm is zero from carbon-14 due to its low energy.           |
| Initially they counted 250,000 cpm on 6/29/00 and after various steps of     |
| decontamination it was reduced to 6,000 cpm after one week.  Daily urine     |
| samples were taken and monitoring continued for a week.  By 7/19/00 counts   |
| per minute were down to 100 cpm.                                             |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37195       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: OYSTER CREEK             REGION:  1  |NOTIFICATION DATE: 07/28/2000|
|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 10:25[EDT]|
|   RXTYPE: [1] GE-2                             |EVENT DATE:        07/28/2000|
+------------------------------------------------+EVENT TIME:        09:41[EDT]|
| NRC NOTIFIED BY:  FREEMAN                      |LAST UPDATE DATE:  07/28/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     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       64       Power Operation  |64       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CEILING OF THE "C" BATTERY ROOM DOES NOT MEET FIRE RATING REQUIREMENTS.      |
|                                                                              |
| OYSTER CREEK NUCLEAR GENERATING STATION HAS DETERMINED THAT THE "C" BATTERY  |
| ROOM CEILING DOES NOT MEET THE REQUIREMENT OF A 3 HR FIRE RATING.  THIS      |
| CONDITION WAS DISCOVERED AS PART OF AN EXTENT REVIEW PER LER 2000-04.  THIS  |
| WAS DETERMINED TO BE REPORTABLE BECAUSE THE CONDITION IS NOT A RECENT        |
| DEGRADATION BUT THE RESULT OF A DESIGN DEFICIENCY WHICH PLACES THE "C"       |
| BATTERY ROOM OUTSIDE DESIGN BASES.                                           |
|                                                                              |
| THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37196       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK              REGION:  1  |NOTIFICATION DATE: 07/28/2000|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 13:07[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        07/28/2000|
+------------------------------------------------+EVENT TIME:        12:30[EDT]|
| NRC NOTIFIED BY:  MARK ABRAMSKI                |LAST UPDATE DATE:  07/29/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MOHAMED SHANBAKY     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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT OUTSIDE DESIGN BASIS BASED ON THE POSITION OF THE MECHANICAL STOP ON    |
| THE "A" RECIRC PUMP SPEED LIMITER                                            |
|                                                                              |
| "The mechanical stop for the 'A' Recirc Pump speed limiter was found to have |
| exceeded the value assumed in the calculation for the flow dependent minimum |
| critical power ratio (MCPR) (K-sub f) in the Core Operating Limit Report     |
| (COLR).  If a Recirc Pump transient (runaway recirc flow) is postulated from |
| a low flow condition, the flow dependent MCPR (K-sub f) may be exceeded.     |
| This could result in exceeding the safety limit MCPR under these postulated  |
| conditions.  This condition is outside the design basis of the plant."       |
|                                                                              |
| This condition was discovered by Engineering and has existed since the last  |
| outage in mid-April of this year.  Evaluation of the 'B' Recirc Pump is      |
| currently in progress.  The licensee informed the NRC Resident Inspector.    |
|                                                                              |
| * * * UPDATE AT 1126 ON 07/29/00 BY BERNARD HORNING TO JOLLIFFE * * *        |
|                                                                              |
| At 1105 on 07/29/00, the licensee has determined that the mechanical stop    |
| for the 'B' Recirc Pump speed limiter also exceeded the value assumed in the |
| calculation for the flow dependent minimum critical power ratio (MCPR)       |
| (K-sub f) in the Core Operating Limit Report (COLR).  If a Recirc Pump       |
| transient (runaway recirc flow) is postulated from a low flow condition, the |
| flow dependent MCPR (K-sub f) may be exceeded.  This could result in         |
| exceeding the safety limit MCPR under these postulated conditions.  This     |
| condition is outside the design basis of the plant.                          |
|                                                                              |
| The licensee informed the NRC Resident Inspector.  The NRC Operations        |
| Officer informed the R1DO Mohamed Shanbaky.                                  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Other Nuclear Material                           |Event Number:   37197       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  NATIONAL INST OF STANDARDS & TECH    |NOTIFICATION DATE: 07/28/2000|
|LICENSEE:  NATIONAL INST OF STANDARDS & TECH    |NOTIFICATION TIME: 14:29[EDT]|
|    CITY:  GAITHERSBURG             REGION:  1  |EVENT DATE:        07/10/2000|
|  COUNTY:                            STATE:  MD |EVENT TIME:             [EDT]|
|LICENSE#:  SNM-362               AGREEMENT:  Y  |LAST UPDATE DATE:  07/28/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |MOHAMED SHANBAKY     R1      |
|                                                |SCOTT MOORE          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  JIM O'REAR                   |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NINF                     INFORMATION ONLY       |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIALLY LEAKING SOURCE                                                   |
|                                                                              |
| A 5mCi Sr-90 source in the form of a brachytherpy seed used for              |
| investigational purposes may be leaking.  There is no known personnel        |
| exposure or spread of contamination involved.   The source was manufactured  |
| by Novoste which is located in GA .  The evaluation will continue to         |
| determine whether the source is actually leaking.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37198       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PALO VERDE               REGION:  4  |NOTIFICATION DATE: 07/28/2000|
|    UNIT:  [1] [] []                 STATE:  AZ |NOTIFICATION TIME: 15:06[EDT]|
|   RXTYPE: [1] CE,[2] CE,[3] CE                 |EVENT DATE:        07/28/2000|
+------------------------------------------------+EVENT TIME:        11:07[MST]|
| NRC NOTIFIED BY:  RUSSELL STROUD               |LAST UPDATE DATE:  07/28/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BILL JONES           R4      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| 1 HOUR SECURITY REPORT                                                       |
|                                                                              |
| SAFEGUARDS SAFETY DEGRADATION RELATED TO THE CONTROL OF CLASSIFIED           |
| DOCUMENT(S)/SAFEGUARDS INFORMATION.  IMMEDIATE COMPENSATORY MEASURES TAKEN   |
| UPON DISCOVERY.  LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR.               |
|                                                                              |
| CONTACT THE HEADQUARTERS OPERATIONS OFFICER FOR ADDITIONAL DETAILS.          |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   37199       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 07/30/2000|
|    UNIT:  [] [2] []                 STATE:  AR |NOTIFICATION TIME: 18:39[EDT]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        07/30/2000|
+------------------------------------------------+EVENT TIME:        16:35[CDT]|
| NRC NOTIFIED BY:  TOM MOSBY                    |LAST UPDATE DATE:  07/31/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BILL JONES           R4      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INDICATION OF REACTOR COOLANT LEAKAGE ON PRESSURIZER HEATER PENETRATIONS     |
|                                                                              |
| "Boron was discovered on the reactor coolant system pressurizer heater power |
| cables.  An inspection of the heater sleeves was performed and it appears    |
| that two heaters (B2 and D2) are leaking.  B2 is on backup heater bank #4    |
| and D2 is on backup heater bank #6. The leakage appears to be the result of  |
| primary water stress corrosion cracking (PWSCC) of either the heater sleeve  |
| or the J-groove weld between the heater sleeve and the pressurizer cladding. |
| The insulation will need to be removed to positively determine which heater  |
| sleeve(s) had been leaking. Currently, Unit 2 is in reduced inventory with   |
| the pressurizer empty.                                                       |
|                                                                              |
| "The pressurizer heater sleeve penetrations were inspected during 2R-13      |
| [between 1/9/99 and 2/25/99] as part of the routine I-600 inspections        |
| performed each refueling outage.  No indication of leakage was evident       |
| during that inspection.                                                      |
|                                                                              |
| "Pressurizer heater sleeve leakage is considered RCS pressure boundary       |
| leakage."                                                                    |
|                                                                              |
| The licensee informed the NRC resident inspector.                            |
|                                                                              |
| * * * UPDATE AT 0052 ON 07/31/00 BY LARRY McLERRAN TO JOLLIFFE * * *         |
|                                                                              |
| After removing insulation from the pressurizer and reactor coolant system    |
| hot legs, the licensee discovered 9 or 10 additional pressurizer heater      |
| sleeves that are leaking and also a hot leg temperature element that is      |
| leaking.  The licensee is continuing to inspect the hot leg penetrations for |
| evidence of leakage.                                                         |
|                                                                              |
| The licensee notified the NRC Resident Inspector.  The NRC Operations        |
| Officer notified the R4DO Bill Jones.                                        |
+------------------------------------------------------------------------------+