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Event Notification Report for July 13, 2001

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           07/12/2001 - 07/13/2001

                              ** EVENT NUMBERS **

38045  38123  38130  38131  38132  38133  38134  38135  38136  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38045       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COLUMBIA GENERATING STATIREGION:  4  |NOTIFICATION DATE: 06/01/2001|
|    UNIT:  [2] [] []                 STATE:  WA |NOTIFICATION TIME: 19:53[EDT]|
|   RXTYPE: [2] GE-5                             |EVENT DATE:        06/01/2001|
+------------------------------------------------+EVENT TIME:        14:02[PDT]|
| NRC NOTIFIED BY:  MYRON BAIRD                  |LAST UPDATE DATE:  07/12/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DALE POWERS          R4      |
|10 CFR SECTION:                                 |                             |
|AESF 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     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INADVERTENT LOSS OF POWER TO A SAFETY BUS                                    |
|                                                                              |
| "At 1402 PST, with Columbia Generating Station in Mode 5, a loss of 230 KV   |
| offsite source (startup transformer) occurred. This resulted in a loss of    |
| voltage to the Div 2 safety related bus (SM-8) which was automatically       |
| reenergized by the 115 KV offsite source (backup transformer).  All plant    |
| systems and components responded as expected. No core alterations were in    |
| progress.  SM-8 was inoperable but energized at the time of the event due to |
| planned outage maintenance.  There was no challenge to the plant shutdown    |
| safety plan as a result of this loss of offsite power.  The loss of power    |
| was a result of a lightning strike offsite on the Bonneville Power           |
| Administration (BPA) electrical grid.  Restoration of the 230 KV source is   |
| pending repairs to damage on the BPA grid.  This notification is being made  |
| pursuant to 10CFR50.72(b)(3)(iv)(B)(8).  This is a valid actuation of an     |
| Emergency AC electrical power system."                                       |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| * * * RETRACTION 1741 FROM SHERMAN TAKEN BY STRANSKY * * *                   |
|                                                                              |
| "Columbia Generating Station hereby retracts a report made to the NRC        |
| Operations Center on June 1st, 2001 at 1953 hours. Event Notification number |
| was 38045. The report was made pursuant to 10 CFR 50.72(b)(3)(iv)(B)(8) and  |
| documented that a lightning strike resulted in a loss of a 230kV offsite     |
| power line to a safety related electrical bus (SM-8) due to a startup        |
| transformer tripping offline. At the time of the event, the plant was        |
| already shut down in Mode 5. The safety related electrical bus was           |
| automatically reenergized by the backup offsite 115 kV electrical source     |
| through the backup transformer.                                              |
|                                                                              |
| "It was assumed at the time of the report that a loss of offsite power was   |
| an actuation of an emergency AC power system. Upon further review, we have   |
| concluded that an automatic bus transfer of offsite power is an alternate    |
| normal power supply and not in the scope of NUREG-1022 as an actuation of an |
| emergency AC power source. Our licensing basis documents also refer to the   |
| emergency diesel generators as the source of all emergency AC power."        |
|                                                                              |
| The NRC resident inspector will be informed of this retraction. Notified     |
| R4DO (Cain).                                                                 |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38123       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON                  REGION:  3  |NOTIFICATION DATE: 07/09/2001|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 13:07[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        07/09/2001|
+------------------------------------------------+EVENT TIME:        09:00[CDT]|
| NRC NOTIFIED BY:  JAMIE BARTSCH                |LAST UPDATE DATE:  07/13/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID HILLS          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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| CONTROL ROOM VENTILATION SYSTEM DECLARED INOPERABLE                          |
|                                                                              |
| The Division 2 Main Control Room Ventilation System was declared inoperable  |
| at 0900 CDT on 7/9/2001 because it was not maintaining the required positive |
| pressure while running in the High Radiation Mode of operation.  The system  |
| was declared operable at 0913 CDT when the required positive pressure was    |
| restored.  During the 13 minute period Division 2 was inoperable, Division 1 |
| Main Control Room Ventilation System was inoperable due to a scheduled       |
| maintenance outage.  Therefore, with both systems inoperable, a condition    |
| existed which could have prevented the fulfillment of the safety function of |
| the Main Control Room Ventilation System needed to mitigate the consequences |
| of an accident.  The cause of the perturbation in control room pressure is   |
| being investigated.                                                          |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
|                                                                              |
| *** RETRACTION FROM STEVEN STRICKLAN RECEIVED BY LEIGH TROCINE AT 0451 EDT   |
| ON 07/13/01 ***                                                              |
|                                                                              |
| The licensee is retracting this event notification.  The following text is a |
| portion of a facsimile received from the licensee:                           |
|                                                                              |
| "On 07/09/01, at approximately 0900 [CDT], the Clinton Power Station (CPS)   |
| experienced a transient situation where, for a period of 13 minutes, the     |
| positive pressure in the Main Control Room (MCR) was compromised.  Based on  |
| this condition, an ENS notification (#38123) was made in accordance with the |
| requirements of 10CFR50.72(b)(3)(v), any event or condition that at the time |
| of discovery could have prevented the fulfillment of the safety function of  |
| structures or systems that are needed to:                                    |
| (A)  shut down the reactor and maintain it in a safe shutdown condition;     |
| (B)  remove residual heat;                                                   |
| (C)  control the release of radioactive material; or                         |
| (D)  mitigate the consequences of an accident."                              |
|                                                                              |
| "An evaluation of the conditions present at the time positive pressurization |
| of the MCR was temporarily interrupted has been performed.  The evaluation   |
| results indicated that the conditions that potentially existed during this   |
| event were bounded by the design basis analysis performed for the [MCR].     |
| The calculated MCR operator thyroid dose for this event was determined to be |
| approximately 23.185 Rem, which is less than the USAR calculated dose of 25  |
| Rem.  The USAR dose is calculated based on a 20-minute time delay in         |
| starting the system in the high radiation mode.  For this event, the high    |
| radiation mode was already in operation.  Whole body and Beta dose for this  |
| event are not governing."                                                    |
|                                                                              |
| "It [has] therefore been demonstrated that, in the event of a design basis   |
| event, time dose impact of the condition as it existed would be bounded by   |
| the current analyses of record.  As such, the safety function would be       |
| fulfilled, and the ENS notification is retracted."                           |
|                                                                              |
| "Although it has been demonstrated that the safety function would be         |
| fulfilled, the situation represented a condition prohibited by Technical     |
| Specifications, and this event continues to be evaluated for reportability   |
| as a Licensee Event Report under 10CFR50.73(a)(2)(i)(B)."                    |
|                                                                              |
| The licensee notified the NRC resident inspector.  The NRC operations center |
| notified the R3DO (Hills).                                                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38130       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 07/11/2001|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 23:01[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        07/11/2001|
+------------------------------------------------+EVENT TIME:        16:50[CDT]|
| NRC NOTIFIED BY:  DAVID BARNETT                |LAST UPDATE DATE:  07/12/2001|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID HILLS          R3      |
|10 CFR SECTION:                                 |                             |
|ADEG 50.72(b)(3)(ii)(A)  DEGRADED CONDITION     |                             |
|AINC 50.72(b)(3)(v)(C)   POT UNCNTRL RAD REL    |                             |
|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |
|ASHU 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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PRIMARY CONTAINMENT DECLARED INOPERABLE - TECH SPEC REQUIRED SHUTDOWN        |
|                                                                              |
| The licensee found a shipping restraint installed on a drywell-to-torus vent |
| pipe bellows, apparently in place since construction (about 30 years).  This |
| device was discovered due to another licensee with similar containment       |
| configuration notifying Monticello of their discovery.  This device would    |
| partially impede axial motion.  The primary containment was declared         |
| inoperable at 1650 CDT on 07/11/01, and removal was initiated.  This is an   |
| 8-hour report under 10CFR50.72(b)(3)(ii)(a) as a degraded condition and      |
| 10CFR50.72(b)(3)(v)(c and d), control of radiation release and accident      |
| mitigation.                                                                  |
|                                                                              |
| The licensee initiated a required shutdown at 2050 CDT on 07/11/01 per       |
| Technical Specification 3.7.A.2.a, as a result of declaring primary          |
| containment inoperable because the drywell-to-torus vent pipe bellows        |
| shipping installation attachments were still installed.  This is a 4-hour    |
| report under 10CFR50.72(b)(2)(i), technical specification required           |
| shutdown.                                                                    |
|                                                                              |
| The licensee notified the NRC resident inspector and intends to notify state |
| and local agencies.                                                          |
|                                                                              |
| ***** UPDATE FROM DAVE BARNETT RECEIVED BY LEIGH TROCINE AT 0039 EDT ON      |
| 07/12/01 *****                                                               |
|                                                                              |
| The four shipping fasteners have been removed from each of the eight         |
| drywell-to-torus vent pipe bellows, and primary containment was declared     |
| operable at 2304 CDT on 07/11/01.  The technical specification required      |
| shutdown was terminated while the reactor was at 90% power.  The licensee    |
| currently plans to restore reactor power to 100%.                            |
|                                                                              |
| The licensee plans to notify the NRC resident inspector as well as the       |
| applicable state and county agencies.  The NRC operations officer notified   |
| the R3DO (Hills).                                                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38131       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PERRY                    REGION:  3  |NOTIFICATION DATE: 07/12/2001|
|    UNIT:  [1] [] []                 STATE:  OH |NOTIFICATION TIME: 00:29[EDT]|
|   RXTYPE: [1] GE-6                             |EVENT DATE:        07/11/2001|
+------------------------------------------------+EVENT TIME:        22:27[EDT]|
| NRC NOTIFIED BY:  FREDERICK W. SMITH           |LAST UPDATE DATE:  07/12/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |DAVID HILLS          R3      |
|10 CFR SECTION:                                 |TAD MARSH            NRR     |
|ACCS 50.72(b)(2)(iv)(A)  ECCS INJECTION         |                             |
|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |
|AESF 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 Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM, HPCS/RCIC SYSTEM INJECTION, AND FULL                |
| BALANCE-OF-PLANT ISOLATION FOLLOWING AN UNSPECIFIED, INTERNAL, ELECTRICAL    |
| TRANSIENT                                                                    |
|                                                                              |
| An unspecified, internal, electrical transient affected balance-of-plant     |
| (BOP) systems and resulted in a feedwater control circuitry problem.         |
| Following this electrical transient, the reactor automatically scrammed from |
| 100% power when reactor vessel water level reached level 3 (178 inches       |
| narrow range).  All control rods fully inserted.  When reactor vessel water  |
| level decreased to level 2 (approximately 120 inches narrow range), the high |
| pressure core spray (HPCS) and reactor core isolation cooling (RCIC) systems |
| automatically initiated and injected into the reactor pressure vessel (RPV). |
| A BOP isolation signal was also received on level 2, and a full BOP          |
| isolation occurred.  In addition, the Division 3 emergency diesel generator  |
| (EDG) automatically started on level 2 (in support of HPCS).  The EDG did    |
| not load, nor was it required to.  The lowest reactor vessel water level     |
| received was 107 inches narrow range.  This was reported to be well above    |
| the top of the active full, which is at 0 inches wide range.                 |
|                                                                              |
| The licensee stated that all safety systems functioned as required.  The     |
| extent and cause of the electrical transient are currently under             |
| investigation.  It was reported that the cause may be related to a possible  |
| auctioneered power supply failure which affected BOP systems and the         |
| feedwater system control circuitry.                                          |
|                                                                              |
| The unit is currently in Mode 3 (Hot Shutdown).  The RCIC system and the     |
| main turbine bypass valves are being utilized for reactor water level        |
| control and RPV pressure control, respectively.  The main steam isolation    |
| valves are open, and the condenser is available as a heat sink.  HPCS has    |
| been placed in standby.  (The quantity of water injected was not available   |
| at the time of this event notification.)  The full BOP isolation has been    |
| reset, and the Division 3 EDG is still running (unloaded).  (The licensee    |
| needs to load the EDG for 1 hour before securing it.)  Containment           |
| parameters were reported to be normal, and there were no challenges to       |
| offsite power.  All emergency core cooling systems and engineered safety     |
| feature systems are currently available.  The feedwater system remains       |
| unavailable pending resolution of the transient's root cause.                |
|                                                                              |
| The licensee notified the NRC resident inspector (who was in the control     |
| room at the time of this event notification).                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38132       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LIMERICK                 REGION:  1  |NOTIFICATION DATE: 07/12/2001|
|    UNIT:  [1] [] []                 STATE:  PA |NOTIFICATION TIME: 05:21[EDT]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        07/11/2001|
+------------------------------------------------+EVENT TIME:        23:30[EDT]|
| NRC NOTIFIED BY:  GENE MICHELSON               |LAST UPDATE DATE:  07/12/2001|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANTHONY DIMITRIADIS  R1      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(3)(v)(A)   POT UNABLE TO SAFE SD  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| DISCOVERY OF AN EXCESSIVE ACCUMULATION OF WATER IN TWO UNDERGROUND FUEL OIL  |
| STORAGE TANKS                                                                |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "[An] excessive accumulation of water [was] discovered in both [the] D11 and |
| D12 underground fuel oil storage tanks.  [There was 33 inches of water in    |
| D11 and 22.5 inches of water in D12.]  This event would prevent both diesel  |
| generators from fulfilling their required safety function.  [Technical       |
| Specification 3.8.1.1, Actions 'b' and 'e,' were] entered, and reportability |
| manual event SAF 1.8 [was also] entered."                                    |
|                                                                              |
| "Actions Taken:  Water has been removed from both [the] D11 and D12          |
| underground fuel oil storage tanks.  [The licensee is] currently performing  |
| [an] operability determination."                                             |
|                                                                              |
| The licensee stated that the unit is remains in the 72-hour limiting         |
| condition for operation due to the ongoing operability determination.        |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38133       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: TURKEY POINT             REGION:  2  |NOTIFICATION DATE: 07/12/2001|
|    UNIT:  [3] [4] []                STATE:  FL |NOTIFICATION TIME: 14:21[EDT]|
|   RXTYPE: [3] W-3-LP,[4] W-3-LP                |EVENT DATE:        07/12/2001|
+------------------------------------------------+EVENT TIME:        10:45[EDT]|
| NRC NOTIFIED BY:  CRAIG MOWREY                 |LAST UPDATE DATE:  07/12/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |PAUL FREDRICKSON     R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3     N          Y       100      Power Operation  |100      Power Operation  |
|4     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNITS IN POTENTIALLY UNANALYZED CONDITION                                    |
|                                                                              |
| "On July 12, 2001, Turkey Point determined that a previous failed            |
| surveillance may have constituted an unanalyzed condition that significantly |
| degraded plant safety. On June 8, 2001, flow damper D-21 was discovered      |
| mispositioned. Damper D-21 controls the amount of recirculation flow in the  |
| Control Room Ventilation System (CRVS), when the system is in the emergency  |
| (recirculation) mode.                                                        |
|                                                                              |
| "The CRVS is designed such that when it shifts to recirculation mode, the    |
| Train B emergency supply fan starts. It draws in a nominal 250 cfm of        |
| outside intake air flow, and a nominal 750 cfm of recirculation air flow,    |
| for a total of 1000 cfm of flow through the HEPA and charcoal filters. If    |
| the Train B fan does not start, the resulting low recirculation flow (less   |
| than or equal to 100 cfm) will cause the Train A fan to start.               |
|                                                                              |
| "During the surveillance it was found that, with the damper open too far,    |
| the recirculation flow stayed so high (about 250 cfm), that even with no     |
| supply fan running, the Train A fan did not receive a low flow start signal. |
| The recirculation flow came from the three running Air Handling Units. As a  |
| result, a single failure of the Train B emergency supply fan could have      |
| caused a loss of emergency supply air forced flow.                           |
|                                                                              |
| "As a result of no forced flow, the outside intake air flow would be         |
| reduced, and the recirculation flow from the Air Handling Units would stay   |
| at about 250 cfm, as measured. By itself, this situation does not            |
| significantly degrade plant safety. If there were no outside air drawn in,   |
| the dose to the Control Room operators would be minimal. However, with no    |
| filtered outside intake air, Turkey Point cannot assure that the Control     |
| Room envelope would be pressurized, the unfiltered inleakage of outside air  |
| may be sufficient to increase the dose to operators."                        |
|                                                                              |
| The NRC resident inspector has been informed of this notification by the     |
| licensee.                                                                    |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   38134       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALVERT CLIFFS           REGION:  1  |NOTIFICATION DATE: 07/12/2001|
|    UNIT:  [1] [2] []                STATE:  MD |NOTIFICATION TIME: 16:17[EDT]|
|   RXTYPE: [1] CE,[2] CE                        |EVENT DATE:        07/12/2001|
+------------------------------------------------+EVENT TIME:        16:17[EDT]|
| NRC NOTIFIED BY:  DROWN                        |LAST UPDATE DATE:  07/12/2001|
|  HQ OPS OFFICER:  BOB STRANSKY                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          NON EMERGENCY         |ANTHONY DIMITRIADIS  R1      |
|10 CFR SECTION:                                 |                             |
|APRE 50.72(b)(2)(xi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OFFSITE NOTIFICATION                                                         |
|                                                                              |
| The licensee will be notifying the Maryland Department of the Environment    |
| (MDE) regarding  positive test results for coliform bacteria in drinking     |
| water samples taken from the educational center. The NRC resident inspector  |
| has been informed of this notification.                                      |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   38135       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  OR DEPT OF HEALTH RAD PROTECTION     |NOTIFICATION DATE: 07/12/2001|
|LICENSEE:  KLB CONSTRUCTION                     |NOTIFICATION TIME: 17:58[EDT]|
|    CITY:  ISSAQUAH                 REGION:  4  |EVENT DATE:        07/12/2001|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PDT]|
|LICENSE#:  ORE-90865             AGREEMENT:  Y  |LAST UPDATE DATE:  07/12/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHUCK CAIN           R4      |
|                                                |JOSEPHINE PICCONE    NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  KEVIN SEIBERT                |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| A Troxler Model 3430 gauge (S/N 28872) was stolen from a storage building in |
| Issaquah, WA. The gauge had been transported to a work site in WA and placed |
| into a locked storage building. The local police department has been         |
| notified (Case #01-05791). The licensee is offering a reward for the return  |
| of the gauge.                                                                |
|                                                                              |
| [See related report 38136]                                                   |
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|General Information or Other                     |Event Number:   38136       |
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| REP ORG:  WA DIVISION OF RADIATION PROTECTION  |NOTIFICATION DATE: 07/12/2001|
|LICENSEE:  KLB CONSTRUCTION                     |NOTIFICATION TIME: 18:33[EDT]|
|    CITY:  ISSAQUAH                 REGION:  4  |EVENT DATE:        07/12/2001|
|  COUNTY:                            STATE:  WA |EVENT TIME:             [PDT]|
|LICENSE#:  ORE-90865             AGREEMENT:  Y  |LAST UPDATE DATE:  07/12/2001|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |CHUCK CAIN           R4      |
|                                                |JOSEPHINE PICCONE    NMSS    |
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| NRC NOTIFIED BY:  TERRY FRAZEE (EMAIL)         |                             |
|  HQ OPS OFFICER:  BOB STRANSKY                 |                             |
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|EMERGENCY CLASS:          NON EMERGENCY         |                             |
|10 CFR SECTION:                                 |                             |
|NAGR                     AGREEMENT STATE        |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| AGREEMENT STATE REPORT                                                       |
|                                                                              |
| "The Oregon licensee reported that a Troxler model 3430 portable gauge,      |
| serial number 28872, containing 10 mCi of cesium-137 and 50 mCi of           |
| americium-241 was stolen from a locked cargotainer at a work site in         |
| Washington state. The Oregon Licensee had transported the portable gauge to  |
| the work site of a Washington licensee in order to complete a sales          |
| transaction. The licensee's employee arrived at approximately 5:30 PM on     |
| July 11. Since no one from the Washington licensee was available on site to  |
| take possession of the gauge, the licensee's employee locked it in a work    |
| site cargotainer. The yellow transport box was reported to be locked. When   |
| the licensee's employee came back around 7:00 AM on July 12, the locks had   |
| been broken and the gauge and several tools had been stolen. The theft was   |
| reported to the City of Issaquah Police. The Washington Radiation control    |
| Program has been in contact with the Oregon Radiation control Program to     |
| coordinate follow-up."                                                       |
|                                                                              |
| [See related report 38135]                                                   |
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